salem, units 1 and 2 - supplemental response to request ... · excore nuclear instrumentation...

FEB to' zo1s LR-N 16-0012 LAR S15-02

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236

PSF:<I NudearLLC

10 CFR 50.90

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Salem Nuclear Generating Station Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and 75 NRC Docket Nos. 50-272 and 50-311

Supplemental Response to Request For Additional Information Re: License Amendment Request Regarding Replacement Of Source Range And Intermediate Range Neutron Monitoring Systems (CAC NOS. MF6065 AND MF6066)

References 1. PSEG letter to NRC, "License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems," dated April 3, 2015 (ADAMS Accession No. ML 15093A291)

2. PSEG letter to NRC, "Supplemental Information Needed for Acceptance of Requested Licensing Action Re: Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems (TAC Nos. MF6065 and MF6066)," dated June 2, 2015 (ADAMS Accession No. ML 15153A 193)

3. NRC letter to PSEG, "Salem Nuclear Generating Station, Unit Nos. 1 and 2 -Request For Additional Information Re: License Amendment Request Regarding Replacement Of Source Range And Intermediate Range Neutron Monitoring Systems (CAC NOS. MF6065 AND MF6066)," dated November 2, 2015 (ADAMS Accession No. ML 15287A141)

4. PSEG Letter to NRC, "Response to Request For Additional Information Re: License Amendment Request Regarding Replacement Of Source Range And Intermediate Range Neutron Monitoring Systems (CAC NOS. MF6065 AND MF6066)," dated November 27, 2015 (ADAMS Accession No. ML 15334A107)

In the Reference 1 letter, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Salem Nuclear Generating Station (Salem), Units 1 and 2. The proposed amendment would revise Technical Specifications (TS} 3/4.3.1, Reactor Trip System, to support the replacement of the existing source range (SR) and intermediate range (IR) nuclear instrumentation.

LR-N16-0012

10 CFR 50.90

In Reference 3, the NRC provided PSEG a Request for Additional Information (RAI) related to the Reference 1 request, dated November 2, 2015. Reference 4 provided the response to the NRC RAI. In the Reference 4 response to Questions 1, 2 and 3, PSEG stated that the qualification summary reports provided by Thermo Fisher Scientific were being formally reviewed and approved as part of issuance of the Design Change Package (DCP).

This letter is to confirm that PSEG has reviewed and accepted the Thermo Scientific qualification summary reports. The qualification summary reports demonstrate that the replacement Source Range and Intermediate Range instrumentation meets the environmental qualification, seismic qualification, and the electromagnetic interference/radio frequency interference (EMI/RFI) requirements of PSEG Specification S-C-DE-NIS-021 0. As requested by the NRC, Enclosure 1 provides the applicable pages from PSEG Specification S-C-DE-NIS-0210 describing the environmental qualification, seismic qualification, and the EMI/RFI requirements.

PSEG has determined that the information provided in this submittal does not alter the conclusions reached in the 10 CFR 50.92 no significant hazards determination previously submitted. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

There are no regulatory commitments contained in this letter.

If you have any questions or require additional information, please contact Mr. Brian Thomas at 856-339-2022.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on FEB 1 o' 2016

· (date)

Respectfully,

CZ_£� � �ohn F. Perry . (/ Site Vice President Salem Nuclear Generating Station

Enclosure 1 - Pages from PSEG Specification S-C-DE-NIS-0210

cc: Mr. D. Dorman, Administrator, Region I, NRC Mr. T. Wengert, NRC Project Manager, Salem NRC Senior Resident Inspector, Salem Mr. P. Mulligan, Chief, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. Cachaza, Salem Commitment Tracking Coordinator

LR-N16-0012

Enclosure 1

Pages from PSEG Specification S-C-DE-NIS-021 0

PSEG NUCLEAR LLC

SPECIFICATION NO.: s .. c .. DE·NIS�0210 SALEM UNIT 1 & 2

Excore Nuclear Instrumentation System (NIS)

IMPORTANT TO SAFETY

Issue for Approval

DETAILED SPECIFICATION REF. NO: N/A

lZ\YES

REV REVISION SUMMARY PREPARER/DATE (Print & Sign)

ONO

QA Reviewer (S&L)

Peer Design Reviewer (S&L)

------------- - ·---�--

Excore Nuclear Instrumentation System Sa/em Generating Station Units 1 & 2 Document No S-C-DE-N/S-0210

Important to Safety

6.3 Equipment Qualification Requirements

Detailed Specification Revision 0

Apri/30, 2014

6.3.1 The NIS equipment shall be qualified by type test, previous operating experience, analysis, or any combination of these three methods, to substantiate that it will be capable of meeting, on a continuing basis, the performance requirements as specified in this detailed specification.

6.3.2 The NlS system S uppl ier shall provide equipment qualification test ing results that include exposure to temperature, humidity, radiation, electromagnetic and radio interference, and seism ic input as described in the following sections . The results of the N!S instrument qualification testing shall be provided as supporting documentation of the equipment qualifications in the form of test plans, methodolog ies , and test reports.

6.4 Environmental Qualification

6.4.1 The new NIS chassis drawers will be installed in existing panels located in the Salem control equipment room. The control equipment room is defined as a Mild Environment; Table 6.4�1 provides the Normal and Abnormal environmental levels to which the NIS components located in the control equipment room shall be qualified.

Table 6.4-1 Normal Operating and Abnormal Conditions

Control Equipment Room

�--:---�-Parameter Normal Normal DBA

Min Max Max Temperature 55 UF 85 UF 85 UF

Humidity 20% 90% 90%

Pressure o.125" we 0.125"WC o.125" we

Radiation, Gamma Rate N/A 0.25 Not Calc

(mr/hr)

Radiation, Gamma TID (r) N/A 87.7 884

6.4.2 The new Excore detectors will be installed in the existing well locations within containment The Containment is classified as a Harsh Environment; Table 6.4-2 provides the Normal and Abnormal environmental levels to which the detectors and interconnecting cables shall be qualified.

Table 6.4-2 Normal Operating and Abnormal Conditions

Containment (Reactor Vessel Area}

Parameter Normal Normal Min Max DBA

Temperature 60 UF <120 UF 351 UF

S-C-DE-NIS-021 0-Rev 0 Page 20 of 85

Important to Safety Excore Nuclear Instrumentation System Salem Generating Station Units 1 & 2 Pocument No �7C-DE-NIS-0210


Apri/30, 2014

6.4.3

6.4.4 ,,.i

' Table 6.4�2

Normal Operating and Abnormal Conditions

Containment (Reactor Vessel Area)

Parameter Normal Normal Min Max DBA

Humidity 20% 90% 100%

Pressure +0.3 psig -1.5 psig 47 psig

Radiation, Gamma (r/hr) N/A 7.16E3 2.07E6

Radiation, Beta (r/hr) N/A N/A 1.35E8

Radiation, Gamma TID (r) N/A 2.51E6 3.18E7

Radiation, Beta TID (r) N/A N/A 1.35E8

Environmental Qualification of the NIS instruments shall be demonstrated in accordance with S-C-ZZ-SD-1419- "Salem Generating Station Environmental Design Criteria" which requires testing per IEEE-323-1974 including any testing margins required by the standard. The tested capability shall meet or exceed the maximum allowed conditions accounting for any internal panel heat rise conditions to ensure that the minimum design limits described in table 6.4.1 and 6.4.2 are maintained.

If the Supplier has previously performed environmental testing under a generic qualification program, the Supplier shall provide a summary report or>certificate of compliance for all testing performed. The testing methodology and criteria used to perform the generic testing and the test results of the testing shall envelope the PSEG requirements and be easily discernable in the test reports.

6.5 EMI/RFI Qualification

6.5.1 The equipment shall be certified to meet or exceed the requirements of EPRI TR-1 02323; Rev. 3 or RG 1.1 &.0 Rev 1 for both transmission and susceptibility. The new equipment shall be qualified through a suitable testing program where EMI/RFI qualification for the NJS equipment assures the equipment has the ability to complete its safety function under all EMC environmental cond it ions that may exist up to and including the time the equipment has finished performing it's safety function.

6.5.2 The following MIL-STD-461 (E) tests are referenced for radiated and conducted emissions. These tests are generally bounded by the requirements of RG 1.180

• CE101

• CE102

• RE101

• RE102

S-C-DE-NIS-021 0-Rev 0 Page 21 of 85

.,i.

Excore Nuclear Instrumentation System Salem Generating Station Units 1 & 2 Document No S-C-DE-NIS-0210

Important to Safety Detailed Specification

Revision 0 Apri/301 2014

6.5.3 If the Supplier has previously conducted EMI/RFl tests under a generic program that adequately demonstrate compliance to the required industry codes and standards, additional testing specific for this application is not required.·

6.5.4 If the Supplier has performed previous testing under a generic qualification program, the Supplier shall provide a llst of standards and or testing to which the equipment was qualified. This may be provided in a qualification summary report or certificate of compliance for all EMIIRFI testing performed.

6.5.5 EMI!RFI considerations to be addressed as part of installation activities will be included as part of the detailed design package performed by PSEG. However, the Supplier shall identify any special installation requirements that are necessary to mitigate EMC interferences and maintain the systems EMIIRFI qualification.

6.6 Seismic Qualification

6.6.1 Equipment shall remain operable before, during and after a Safe Shutdown Earthquake (SSE).

6.6.2 The seismic/dynam'ic qualification of the NIS equipment shall be performed using a Required Response Spectra (RRS) that bounds the SGS Seismic Spectra shown in Attachments K and L, and be performed fn accordance with IEEE 344.

::e. 6.3 The tested equipment shall be a rep-resentative unit inCluding. all hecessa ry cable/conduit connections to simulate the field mounting configurations-to account for the weight of cables, conduits and fittings.

6.6.4 The mounting details and the orientation of tested equipment shall simulate the inservice mounting details and orientation as close as practical.

6.6.5 For both OBE/Upset and SSE/Emergency/Faulted tests, the test response spectra shall envelop the RRS with at least 1 0% margin.

6.6.6 Any differences in the design of the equipment as delivered from the configuration of the equipment as tested shall be justified by the Supplier.

6.6.7 The analysis or test shall be performed for the Safe Shutdown Earthquake (SSE) case and the Operating Basis Earthquake (OBE) case at the floor response spectra provided in Attachments K and L of this specification. The figures are applicable to the mounting location of the equipment. For the SSE case, 3% damping shall be applied. For the OBE case, 2% damping shall be applied. The equipment shall operate and perform their functions during and after they have been subjected to five (5) OBE and one (1) SSE tests.

6.6.8 If the Supplier has previously performed testing under a generi.c qualification program, then the Supplier shall provide a summary report or certificate of compliance for all testing performed. The testing methodology atid criteria used in the generic testing shall envelope the PSEG requirements and the SGS Seismic Spectra.

S-C-DE�NIS-0210-Rev 0 Page 22 of 85

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ScC-DE-NIS-0210-Rev 0

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Revision 0 April 30, 2014

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Attachment 7 page 46

salem, units 1 and 2 - supplemental response to request ... · excore nuclear instrumentation...

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