ATTACHMENT 2

To

Letter from M. L. Marchi (WPSC)

to

Document Control Desk (NRC)

Dated

February 15, 1999

Proposed Amendment 159

Strike-Out TS Pages:

TS iv TS 6.1-1 TS 6.2-1 TS 6.5-1 TS 6.5-2 TS 6.5-3 TS 6.5-4 TS 6.5-5 TS 6.5-6 TS 6.6-1 TS 6.7-1

9903020172 990215 PDR ADOCK 05000305 P PDR

GBN1JCI N:\GROUP\NUCLEAR\WPFILES\LIC\NRCOPA159.WPDI

0 * Section Title Rage

6.5 ee.wand-A.diteleted...................6.. .5

....... rutin ............... . .

G.5.a.2 Composition ............. 5.

... G eepon ibiliti ... .... ..... 5 1

.G .7 Authusit, . 4 4 . 4 . .... 0 Reco ds . . . . . . G. 2

...... 1 functio..R d . . . . . ....

G... .G.Q orum... .5 4. 0.....0 Adt s1t . . . . . .. G.5..

. . .0 Aut u.t ... . . ... . ..... . . . .8 G

.5 .0. Rec .d . . 4

6.6 ... prtbf.-Ee.tsDeleted........... . ........... 6.6-1 6.7 Safety Limit Violation ................. 6.7-1 6.8 Procedures. .. ...... .... . ................. 6.8-1 6.9 Reporting Requirments ........... . ... .......... . 6.9-1

6.9.a Routine Reports..... ..... ........ 6.9-1 6.9.a.1 Startup Report....... . . .6.9-1 6.9.a.2 Annual Reporting Requirements ... 6.9-1 6.9.a.3 Monthly Operating Report..........6.9-3

6.9.b Unique Reporting Requirements..... 6.9-3 6.9.b.1 Annual Radiological Environmental

Monitoring Report....... ...... 6.9-3 6.9.b.2 Radioactive Effluent Release Report 6.9-3 6.9.b.3 Special Reports. .......6.9-3

6.10 Record Retention.. ....6.10-1 6.11 Radiation Protection Program.................... 6.12 System Integrity.. 6.13 High Radiation Area...... ... 6.14 Post-Accident Sampling and Monitoring....... 6.15 Secondary Water Chemistry.......... 6.16 Radiological Effluents... 6.17 Process Control Program (PCP) .61

6.18 Offsite Dose Calculation Manual (ODCM) . .. 18.

6.19 Major Changes to Radioactive Liquid, Gaseous .. ~~~~~~~~ ~ ~ ~~ ..... .................. . . .. 6.. . 1 1 -1.

e.... ...6.19-1 ... ... . . ... ... ... .. .. ... ... . . . . . .. . . ... . . . . 6 . 3

.... .... ... .... ... .... ... .... ... .... ... .: ... ..... ........ ...6 . 1 5 .. ~~ . .. .... ......... 6 ..... ... .... ... .... ... ... . .. .... . . 6 . 8

7/8.0 Deleted

Amendment No. 1-7 TS iv 96/69/96

0

6.0 ADMINISTRATIVE CONTROLS

6.1 RESPONSIBILITY

ai The Manager - Kewaune

this responsibility

Amendment No. 99 04/21/93TS 6.1-1

6.2 ORGANIZATION

a. Off-Site Staff

The off-site organization for plant management and technical support shall be as described in the Operational Quality Assurance Program Description.

b. Facility Staff

The plant organization shall be as described in the Operational Quality Assurance Program Description.

1. Each on-duty shift complement shall consist of at least:

A. One Shift Supervisor (SRO) B. Two licensed Reactor Operators C. OeTwoNucler Auxiliary Operator" D. One Equpmeat-OpertheDeleted E. One Radiation Technologist

2. While above COLD SHUTDOWN, the on-duty shift complement shall consist of the personnel required by TS 6.2.b.1 and an additional SRO.

3. In the event that one of the shift members becomes incapacitated due to illness or injury or the Radiation Technologist has to accompany an injured person to the hospital, reactor operations may continue with the reduced complement until a replacement arrives. In all but severe weather conditions, a replacement is required within two hours.

4. At least one licensed operator shall be in the control room when fuel is in the reactor.

5. Two licensed operators, one of which shall be an SRO, shall be present in the control room when the unit is in an operational MODE other than COLD SHUTDOWN or REFUELING.

6. REFUELING OPERATIONS shall be directed by a licensed SRO assigned to the REFUELING OPERATION who has no other concurrent responsibilities during the REFUELING OPERATION.

7. When the reactor is above the COLD SHUTDOWN condition, a qualified Shift Technical Advisor shall be within 10 minutes of the control room.

Amendment No. 99 TS 6.2-1 94/21/93

6.5 REVfEW-A-AUfFDel eted

1. Function

The PO1C shall funct on to ad;Iseth M6a.ager Kewaune Plansit o ..... e.s.....t ed...............t..

2. Cuou noitioun

4. t~1eetin~ FrequoncyTh .. .O~ . h~ t1 e ... t. ...to.e.e......... ojt a d s orv

......... y th ...ha........... ..an;i 4-4

............. ..u o......m

A ........... of...... the.. ....C shl consist of t ... ~ i h t7 i

(V Qr.nr;zThilitisaz

.. h....O.C...h... .~~r s b t 1m

............. e e~iV~d~4rmtt~ta afctncla

.. .. ... ... ..... .

.. R..wo...prpse....so.teTahfla &i~atos

D. :: ReiewoaitpseshiVmdiiain o ln yt

TS 6.5-1Amendment No. +*f

041/97/94

0 0

f.~~~~ .......... .... ..........,~st~h~eu~t Pa, r .... .h e.. .s e t v ................. u i ~

......... ......~ a e u t d by t .. ... ........ t~ uc ea $~fety fl view .................ee.

.. ..... ... ................. .................

... R eco~ end to the ~1...............................ppro~ of ~ c~sided uderS ~ thru~h S C5.PA.E

13.~.... .ak .e .....a .s .... .ear t....t............h I .......... .n d .. ........ .....G .... ... .... ... ... ... a ! .. .. .. .. .. .. .. .. .. .. .. ...... ... ... .

.X.4 .................... ...... ..... .. ................. .. .. .... ... .... ........... .... .. ........................... .......... ............................................. ........ .................. . .............. ........................................................................... ............................ on i 6 A

................ P, r . u .:4: ...... ...... ....... .... ... . .......... .. ................

TS 6.5-2Amendment No. i-O-7

*&l'7/94

SNuclear ....ty...vie...d ....t................C ... .... ... ...

.......... C....................................t..................~ ...... ...... ...... ...... ..... ...... ...... ...... .....

........ ....... ......

Th $A halb op&e f ~t:u.~j...k~jf mtdt

.. .. t ................~..om a~ a fli te tch ,I

...... ..... ..... .....

rah e be of te .S~ shal ....... aad.....~r ei~~~~in...... .........l.......fe l.........dit.....~l] hav

~ ~ wii of ive yeas .t~hica .e....ce f ....... ..... .. ... ...a ... ... .... ... .... .... .i. .. .. . .n .i .r .a ...... .n ..... ..... .....

3......... .... Alt.............. ate.s....

. ...... wl .i d ejl e x p er ..v c t. th &i~ RNS R A C. !

TS 6.5-3Amendment No. i-ff7

041'71O94

............... ................

:::. .07 M el t ......................

........ ......liic a~1est oc ~.~~ ho h ...........

.. .jio u ................ .h l Z A .. i] ... n ....... .t ~ t. .h ..... ....................... .............. in lu i v t e l ta . N i g ................

the ~ ~ ~ ~ ~ ~ ~ ~ ~ ..u~u .hi] .ae1nrso~iit .oi ..h..> ......

.. . ...... . . ... .. ... .....

.............. view

.............. ~j) ~ d~es qpi~1 ~~y~te~~s! .............................eted.....t..

......... . .................. I .....5 . ~ . . . .. . . w .. s ~

.4.k rc1:e upag. irecna Spcfvain 1 ;;.uot-

.... ... ... a.. id e petd .. pe fr a ce o 1 n ..hat......t.........s.fe.y.

..... .eot ..ern ...CP~ADC rV N S

... Re iort ..o.......... any ....ca io .f .n .n n i e .............. .

:~ a~pe tof deign or peratin....s.et....at.d...u.....

.............. , .. ...... ....... ..... n t. I.~~~~~ ~~~~ Iwo~t Ii~ metn i ~ ueso h.O

TS 6.5-4Amendment No. WO

04 7e94

......... .......... s. ssem~o~mthdofoortonta

.... ................l..... am. .~r:A Q ~t e~ area ......t.......................... I .. th

NA r te Zenor o nyof lr ~wh th N~ACre.......

... The... .....oic~ .........ta ...ioi 1 ... ~ .. d th e

~~~~ LI phoit

...... flet#d

Records ~ ~ ..... ..... ......~is hl e.~pre,4~tyJ~ ......... bu e ....... f.o..l l......o... w s.. ....... ....

......... .......... ... f. .....h ............... ..... f w r e d t h $ r i r ~ Offic .. to ihj . h ...... o~sw hi .. .... fl..ig a mee*U Iul Ogjft

B~~ ~eports of revi............by.................o gh TZ G I t1 foKss ote Sno opn ff h &A *..*t~ 14.ay~ ollow 1~ coplet...ofthe..... w

Amnmnro e ...... 6 .5 -5...........9.

~nan psit~ns yesomsbleforthe arAmedted o wtIff2

IS 6.5-6 04/07/94

6.6 RPRAL V~Seee T.... .... . 1. ..................................................

................. T ... 1 si h~l.en tfe rJ e ~ ur~ tcIp~ sa tt J ... ... ... ...... ........~7

Amendment No. 99 04/21i793IS 6.6-1

0 *

6.7 SAFETY LIMIT VIOLATION

The following actions shall be taken in the event a safety limit is violated:

a. The reactor shall be shut down and operation shall not be resumed until authorized by the Commission.

b. The Report shall be prepared in accordance with T0 6-10 CFR 50.72 and 0 .CFR 50.73.

Amendment No. 99 TS 6.7-1 04/21/93

ATTACHMENT 3

To

Letter from M. L. Marchi (WPSC)

to

Document Control Desk (NRC)

Dated

February 15, 1999

Proposed Amendment 159

Affected TS Pages:

TS iv TS 6.1-1 TS 6.2-1 TS 6.5-1 TS 6.5-2 TS 6.5-3 TS 6.5-4 TS 6.5-5 TS 6.5-6 TS 6.6-1 TS 6.7-1

GBNUCI N:\GROUP\NUCLEAR\WPFILES\LIC\NRC\PAl59.WPD

Section

6.5 6.6 6.7 6.8 6.9

6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17 6.18 6.19

S Iift3_

Deleted . . . . . . . . . . . . . . . . . . . . . Deleted . . . . . . . . . . . . . . . . . . . ...... Safety Limit Violation . . . . . . . . . . Procedures . . . . . . . . . . . . . . . . . . . . . . . Reporting Requirements . . . . . . . . . . . . . . . . . 6.9.a Routine Reports . . . . . . . . . . . . . . . .

6.9.a.1 Startup Report . . . . . . . . . . . 6.9.a.2 Annual Reporting Requirements . . . 6.9.a.3 Monthly Operating Report . . . . . .

6.9.b Unique Reporting Requirements . . . 6.9.b.1 Annual Radiological Environmental

Monitoring Report . . . 6.9.b.2 Radioactive Effluent Release Report 6.9.b.3 Special Reports . . . .

Record Retention . Radiation Protection Program System Integrity High Radiation Area Post-Accident Sampling and Monitoring . . . . Secondary Water Chemistry Radiological Effluents Process Control Program (PCP) Offsite Dose Calculation Manual (ODCM) . . . Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems.

- 6.5-6 6.6-1 6.7-1 6.8-1 6.9-1 6.9-1 6.9-1 6.9-1 6.9-3 6.9-3

6.9-3 6.9-3 6.9-3

. . . . 6.10-1

. . . . 6.11-1

. . . . 6.12-1

. . . . 6.13-1

. . . . 6.14-1

. . . . 6.15-1

. . . . 6.16-1

. . . . 6.17-1

. . . . 6.18-1

6.19-1

7/8.0 Deleted

TS ivProposed Amendment No. 159

02/15/99

S

6.0 ADMINISTRATIVE CONTROLS

6.1 RESPONSIBILITY

a. The Manager - Kewaunee Plant operation and shall dlelegat responsibility during his abse

b P. The Manager-Kewaunce Plant,

TS 6.1-1

)lant this

Proposed Amendment No. 159 02/15/99

I

6.2 ORGANIZATION

a. Off-Site Staff

The off-site organization for plant management and technical support shall be as described in the Operational Quality Assurance Program Description.

b. Facility Staff

The plant organization shall be as described in the Operational Quality Assurance Program Description.

1. Each on-duty shift complement shall consist of at least:

A. One Shift Supervisor (SRO) B. Two licensed Reactor Operators C. Two Nuclear Auxiliary Operators D. Deleted E. One Radiation Technologist

2. While above COLD SHUTDOWN, the on-duty shift complement shall consist of the personnel required by TS 6.2.b.1 and an additional SRO.

3. In the event that one of the shift members becomes incapacitated due to illness or injury or the Radiation Technologist has to accompany an injured person to the hospital, reactor operations may continue with the reduced complement until a replacement arrives. In all but severe weather conditions, a replacement is required within two hours.

4. At least one licensed operator shall be in the control room when fuel is in the reactor.

5. Two licensed operators, one of which shall be an SRO, shall be present in the control room when the unit is in an operational MODE other than COLD SHUTDOWN or REFUELING.

6. REFUELING OPERATIONS shall be directed by a licensed SRO assigned to the REFUELING OPERATION who has no other concurrent responsibilities during the REFUELING OPERATION.

7. When the reactor is above the COLD SHUTDOWN condition, a qualified Shift Technical Advisor shall be within 10 minutes of the control room.

Proposed Amendment No. 159 TS 6.2-1 02/15/99

0

6. 5 DELETED

TS 6.5-1 through TS 6.5-6Proposed Amendment No. 159

02/15/99

6.6 DELETED

TS 6.6-1Proposed Amendment No. 159

02/15/99

0g g'

6.7 SAFETY LIMIT VIOLATION

The following actions shall be taken in the event a safety limit is violated:

a. The reactor shall be shut down and operation shall not be resumed until authorized by the Commission.

b. The Report shall be prepared in accordance with 10 CFR 50.72 and 10 CFR . 73.

Proposed Amendment No. 159 TS 6.7-1 02/15/99