LR-N15-0080, Supplement to License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)

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Supplement to License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)
ML15100A406
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/10/2015
From: Jamila Perry
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR S14-03, LR-N15-0080
Download: ML15100A406 (7)
v • d • e


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 APR 1 0 t015..

LR-N 15-0080 LAR S14-03 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 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 Nuclear LLC 10 CFR 50.90

Subject:

Supplement to License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors during Mode 6 (Refueling)

Reference:

LR-N14-0185, "License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors during Mode 6 (Refueling)," dated March 9, 2015 On March 9, 2015, PSEG Nuclear LLC (PSEG) submitted a license amendment request (LAR) to Renewed Facility Operating License Nos. DPR-70 and 75 for Salem Generating Station Units 1 and 2 to isolate unborated water sources and use Gamma-Metrics Post-Accident neutron monitors during Mode 6 (Refueling). Subsequent to this submittal, PSEG determined that the LAR did not contain Technical Specification (TS) markup pages for the affected TS Bases Index. Also, the LAR did not update Surveillance Requirement 4.9.2 numbering to reflect the Limiting Condition for Operation (LCO) numbering change. The associated markup pages are included as Attachment 1 to this letter.

The TS Surveillance Requirement number and Bases Index changes do not affect the Technical Analysis or No Significant Hazards Consideration conclusions contained in the LAR.

There are no regulatory commitments contained in this letter.

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

Document Control Desk LR-N15-0080 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

APR 10 015 Executed on _________ _

(Date)

Respectfully, fl - f1 I

"V""**-

John F. Perry Site Vice President Salem Generating Station

Attachment:

1.

Technical Specification Bases Index (mark-up pages)

Technical Specification LCO 3.9.2 (mark-up pages) cc:

Mr. D. Dorman, Administrator, Region I, NRC Ms. C. Sanders-Parker, Project Manager, NRC NRC Senior Resident Inspector, Salem Mr. P. Mulligan, Manager IV, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. Cachaza, Salem Commitment Tracking Coordinator APR 1 0 2015

LR-N15-0080 TECHNICAL SPECIFICATION PROPOSED CHANGES LAR S14-03 The following Technical Specifications for Renewed Facility Operating License DPR-70 are affected by this change request:

Technical Specification Bases Index TS LCO 3.9.2 XV 3/4 9-2 The following Technical Specifications for Renewed Facility Operating License DPR¥75 are affected by this change request:

Technical Specification Bases Index TS LCO 3.9.2 XV 3/4 9-2

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3 I 4. 9.1 BORON CONCENTRATION

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UAilJo.eArG.D w,q*r,e.5ov..eci /Sol../'1-'rtOAJ lML.V.GS 3/4.9.2â INSTRUMENTATION 3/4.9.3 DECAY TIME 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4.9.6 MANIPULATOR CRANE 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF B 3/4 9-1 8 3/t.J 'l-1 b B 3/4 9-lb B 3/4 9-1-b-c B 3/4 9-1"""'

ot:.

B 3/4 9-3 B 3/4 9-3 B 3/4 9-3 B 3/4 9-3 ISOLATION SYSTEM B 3/4 9-4 3/4.9.10 WATER LEVEL REACTOR VESSEL and AND 3/4.9.11 *STORAGE POOL 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOW.N MARGIN 3/4.10.2 GROUP HEIGHIJ' I INSERTION AND PO\\IIER DISTRIBUTION LIMITS 3/4.10.3 PHYSICS TESTS 3/4.10.4 NO FLOW TESTS SALEM UNI'r 1 XV B 3/4 9-4 B 3/4 9-4 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1

./

Amendment No, 262

REFUELING OPERATIONS INSTRUMENTATION LIMITING CONDITION FOR OPERATION oe£lM6L£.

3.9.2 A minimum;'(wo source range neutron flux monitors shall be opereting, each wih Gef:tt+R-'+&Id-a+-rtei'l'-tt

' nl"'l<lree-eet'14fifl*Fe-i-reeFA elflel one wiH'1 audible indication iA the containment and control rcoAl.

APPLICABILITY: MODE 6.

ACTION:

WHh the requircfficnte of the above epeoifioatioA not satisfied, immediately suspend all operations involving CORE ALTE:R/\\TION£ or pooiti'Ve reactivity changes. The provisions of Speci*fioation 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

JNS'fY

... I 2 CALI.t1RATIOIU lo.

tr.

A CHANNEL FUNCTIONAL TEG"f in accordance with the Surveillance Q... -b.

Frequency Control Program, and A CHANNEL CHECK in accordance with the Surveillance Frequency Control Program during CORE ALTERATIONS.

SALEM-UNIT i 314 9-2 b Amendment No. 299

INDEX BASES SECTION 9

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/t-1* 9, z. 1 v.v.f2,o.e,".lr(,t/) WA1E..e SoLJ;('c4: 15X>L14/ID.. v t.I.4<-Vi6'S 3/4.9.2.;1. INSTRUMENTATION 3/4.9.3 DECAY TINE 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMNUNICATIONS 3/4.9.6 MANIPULATOR CRruE 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF B 3/4 9-1 0 '3/<1 qJ b B 3/4 9-1b B 3/4 9-1_

c B 3/4 9-1.e-d B 3/4 9-3 B 3/4 9-3 B 3/4 9-3 B 3/4 9-3 ISOLATION SYSTEM E 3/4 9-4 3/4.9.10 and 3/4.9.11 WATER LEVEL REACTOR VESSEL Al.'ID STORAGE POOL 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM 3/4.10 SPECIAL TEST EXCEPTIONS B 3/4 9-4 B 3/4 9-4 3/4.10.1 SHUTDOWN MARGIN B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4.10.3 PHYSICS TESTS 3/4.10.4 NO FLOW TESTS SALElM UNIT 2 XV B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 Amendment No. 2L:4

3.9,2,2 REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONPITiillLEQR.DPERATI Of'£R.A6<.£

  • 3.9.2,'\\sa minimuFr(lo source range neutron flux monitors shall be opefatil"'§, each with continuous visual indieatieA iA the eeffiFel reem al"'d oAe with audible indication in the eeffiafAmenF.ana eoAtFol Foam.

APPLICABILITY: MODE 6.

ACTION:

a.

With one of the above required monitors inoperable, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity oF!anges. Ar>OrrtoJ\\JS, t.uS£f-T i

b.

With beth ef the required monitors inoperable, determine the boron eoneentfetion ef tho roaster ooolant S)'stom at least onoe F'OF 12 hou;:s.

c.

The provisions of Specification 3.0.3 are not applicable.

S-UlliLEILLANCE REQUIREMENTS Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK in accordance with the Surveillance Frequency Control Program, and 1

..,.,.  - z.

flJ:;. J;:;..._,

CAL ti,3,.¢...A'Tie.1r\\J

b.

A CHANNEL FUNCTIONAL TES.:r in accordance with the Surveillance Frequency Control Program.

SALEM-UNIT 2 3/4 9-2 b Amendment No. 282

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