ML20148B671

Informs That Tech Spec Change Request Re Standby Liquid Control Sys Will Be Submitted by 880501

ML20148B671
Person / Time
Site:	Oyster Creek
Issue date:	03/16/1988
From:	Thorpe J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
C300-88-291, NUDOCS 8803220082
Download: ML20148B671 (2)

Text

GPU Nuclear Corporation i Nuclear o sa"scan,'. "N 201-316-7000

".,s.,o,es.

TELEX 136-482 Writer's Direct Dial Nurnber:

C300-88-291 March 16, 1988 Document Control Desk U.S Nuclear Regulatory Comission Washington, D.C. 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 10 CFR 50.62 (c)(4)

The NRC Staff, by letter dated February 18, 1988, requested that GPU Nuclear submit a Technical Specification Change Request (TSCR) that will provide limiting conditions for operation and surveillance requirements for the Standby Liquid Control System by March 31, 1988. The purpose of this letter is to infom the Staff that the requested submittal date does not allow sufficient time for the preparation and approval of the TSCR and that GPUN intends to submit the infomation by May 1,1988.

i Very truly yours ,

li w J. R. Thorpe Director, Licensing & Regulatory I

Affairs JRT/JDL/jbw 6501 f l

8803220082 880316 DR ADOCK 05000219 0{

0 DCD >

GPU Nuclear Corporation is a substd;ary of General Pubhc Utilst<es Corporation I\

x_ .~ -

cc: LMr. William T. Russell, A&ninistrator Region I . '

U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406-NRC' Resident Inspector _ .

= Oyster Creek Nuclear Generating Station Forked ~ River, NJ 08731 Mr. Alex Dromerick, Jr.

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 I

i

I 4 4 UNITED STATES

... Y N NUCLEAR REGULATORY COMMISSION g ,a WASHING TON. D. C. 20555 PEB181988 Docket No. 50-219 s

Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

SUBJECT:

STANDBY LIQUID CONTROL SYSTEM COPPLIANCE WITH THE ATWS RULE - 10 CFR 50.62(c)(4) - OYSTER CREEK NUCLEAR GENERATING STATION (TAC NO. 66126) l By letter datad September 3, 1987 and December 30, 1987, GPU Nuclear i Corporation provided infonnation concerning the requiren.ents of 10 CFR 50.62 for Oyster Creek Nuclear Generating Station. Based on our review of this infonnation, we have concluded that the proposed design for the Standby Liqu !

Control System is consistent with the requirement of 10 CFR 50.62(c)(4) and h acceptable. This is discussed in the enclosed Safety Evaluation. Other matters related to the requirements of 10 CFR 50.62 will be the subject of a future letter from the staff when the evaluation is completed.

It is requested that you submit a Technical Specification Change Request that will provide limiting conditions for operations and surveillance requirenents

for the Standby Liquid Control System as discussed in the staff's Safety Evaluation. You are requested to respond to this request by March 31, 1988 so l that the staff can complete its review in accordance with the schedule completion date.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore; OMB clearance is not required under P.L.97-511.

Sincerely, I f W Alexander W. Dromerick, Project Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation l

l

Enclosure:

As stated l

cc w/ enclosure See next page G

Mr. P. B. Fiedler Oyster Creek Neelear

.. ' Oyster Creek Nuclear Generating Station Generating Station

' ~

CC:

Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trtwbridge e/o U.S. NRC 2300 N Street, W Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 08731 J.B. Libeman, Esquire Ccmissioner Bishop, Libeman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering U.S. Nuclear Regulatory Comission Department of Environmental Protection 631 Park Avenue .

CN 411 -

King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08625 BWR Licensing k nager GPU Nuclear Corporation s, 1 Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625

, Nyor

! Lacey Township -

l 818 West Lacey Road l Forked River, New Jersey 08731 1

Licensing Manager Oyster Creek Nuclear Generating Station

Mail Stop: Site Emergency Bldg. '

P. 0. Box 388 Forked River, New Jersey 08731 l

l is

l 33 ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT 0P PEGULATION RELATING TO 10 CFR 50.62(c)(4), ATWS RULE GPU FUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219

1.0 INTRODUCTION

In letters dated September 3, 1987 (5000-87-1361) and Decenber 30, 1987 (5000-87-1447) GPU Nuclear Corporation submitted a description of its plans for implementing the requirements of 10 CFP 50.6? at Oyster Creek Nuclear Generating Station. The proposed Standby Liquid Control System (SLCS) is designed to supply 30 gpn of enriched sodiun pentaborate solution (35 atom percent of B-10) to the reactor vessel to meet ATWS requirements.

2.0 EVALUATION The SLCS description provided by GPU 'or Oyster Creek has been reviewed by the staff against the requirements of the ATKS rule (10 CFR 50.6?fe)(4), and Generic Letter 85-03, "Clarification of Equivalent Control Capacity for Standby Liquid Control Systems," dated January P8,1985. The licensee will increase the boron enrichment to a minimum of 35 aton percent of B-10, and proposes to supply 30 gpn of a minimum 15 weight percent of sodium pentaborate solution to the reactor vessel. Accounting for the physical size of the Oyster Creek reactor vessel which is 213 inches inside diameter, the aforementioned flow / enrichment combination satisfies the ATWS Rule equivalency requirement which is based upon 86 gpm pump flow, 13 weight percent sodium pentaborate and 19.8 atom percent B-10, and a 251 inch diameter vessel, es discussed in Generic Letter 85-03. The proposed design is therefore l acceptable.

The licensee should confirm that surveillance and positive verification will be perfonned periodically (once per month) to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g., boron or boric acid are added to the storage tank, isotopic enrichment of B-10 in the solution should also be verified. This comitment as well as periodic veri-fication of the 30 gpm flow rate should be reflected :n the plant Technical Specifications.

3.0 CONCLUSION

S The description of the proposed SLCS operation by GPU Nuclear Corporation for the Oyster CNek Nuclear Generating Station in letters dated September 3,1987 and Decenber 30, 1987 is accepthble because it is consistent with the equivalency requirements of 10 CFR 50.62(cIldl.

Principle Contributor: M. McCoy S  ??7

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