ML20246F913

Forwards Request for Addl Info Re 880620 Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4 9.3, RCS Pressure/Temp Limits & Overpressure Protection Sys, Respectively

ML20246F913
Person / Time
Site:	Wolf Creek
Issue date:	08/21/1989
From:	Pickett D Office of Nuclear Reactor Regulation
To:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
References
TAC-68507, NUDOCS 8908310169
Download: ML20246F913 (4)

Text

_ _

.. August 21, 1989 Docket No. 50-482 Mr. Bart D. !!ithers President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING R POSED REVISIONS ,

1 TO TECHNICAL SPECIFICATIONS 3/4.4.9.1 - REACT 0,5 COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITS AND 3/4.4.9.3 - OVERPRESSURE PROTECTION SYSTEM (TAC NO. 68507)

Reference:

Wolf Creek Letter ET 88-0084 dated June 20, 1988 from John A. Bailey to NRC The staff is currently reviewing the referenced letter concerning proposed Technical Specification changes for reactor coolant system Pressure / Temperature Limits (3/4.4.9.1)andOverpressureProtectionSystems(3/4.4.9.3). In order to continue its review, the staff requests additional information identified in the enclosure.

This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511. We request that you respond to the enclosure within 60 days following receipt of i W letter.

Sincerely,

/s/

Douglas V. Pickett, Project Manager Project Direc.torate IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear P.eactor Regulation

Enclosure:

As stated  :

cc w/ enclosure:

See next page DISTRIBUTION Docket Fije:. NRC PDR Local PDR PD4 Reading G. Holahan ADR4 F. Hebdon P. Noonan Project Manager 0GC-Rockville E. Jordan B. Grimes ACRS(10) PD4 Plant File W. Hodges DOCUMENT NAME: WC LTR gg i t PD4/P SRXB ! PD4/Qd 4PD4/LA PNoonan DPick  : j MWHo es FHebdon 08/t5/89 08/15/89 08/af/89 08/4/89 l 8908310169 890821 PDR ADOCK 05000482

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Uc Docket'No. 50-482.

Mr. Bart D. Withers President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS 3/4.4.9.1 -_ REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITS AND 3/4.4.9.3 - OVERPRESSURE PROTECTIONSYSTEM(TACNO.68507)

Reference:

Wolf Creek Letter ET 88-0084 dated June 20, 1988 from John A. Bailey to NRC The staff is currently reviewing ~the referenced letter concerning proposed Technical. Specification changes for reactor coolant system Pressure / Temperature Limits '(3/4.4.9.1) and Overpressure Protection Systems (3/4.4.9.3). In order to continue its review, the staff requests additional information identified in l the enclosure.

This request for information affects fewer than 10 respondents; therefore, OMB clearance _is not required under P.L.96-511. We request that you respond to

.the enclosure within 60 days following receipt of this letter.

Sincerely, 3, ,, ./ i - . tJ-A Douglas V. Pickett, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulatio..

Enclosure:

l~ As stated Jcc w/ enclosure:

See next page

- -- -- L---- .____m____.__,__._________.,__.__ _____

-Mr. Bart D.~ Withers Wolf Creek Generating Station Wolf Creek Nuclear Operating Corporation Unit No I cc:

Jay Silberg, Esq. ..

Mr. Gerald Allen Shaw; Pittman,'Potts & Trowbridge Public Health Physicist 1800 M' Street, NW Bureau of Air Quality & Radiation Washington, D.C. 20036 Control Division of Environment Chris R. Rogers, P.E. Kansas Department of Health Manager, Electric Department and Environment Public Service Commission Forbes Field Building 321 P. O. Box 360 Topeka, Kansas 66620 Jefferson City, Missouri 65102 Mr. Gary Boyer, Plant Manager Regional Administrator, Region III Wolf Creek Nuclear Operating Corp.

U.S. Nuclear Regulatory Commission P. O. Box 411 .

799 Roosevelt Road Burlington, Kansas 66839 Glen Ellyn, Illinois 60137 Regional Administrator, Region IV Senior Resident Inspector / Wolf Creek U.S. Nuclear Regulatory Commission c/o U. S. Nuclear Regulatory Commission Office of Executive Director P. O. Box 311 for Operations Burlington, Kansas 66839 611 Ryan Plaza Drive, Suite 1000 Mr. Robert Elliot, Chief' Engineer Utilities Division Mr. Otto Maynard, Manager l Kansas Corporation Commission Regulatory Services 4th Floor - State Office Building Wolf Creek Nuclear Operating Corp.

l- Topeka, Kansas 66612-1571 P. O. Box 411 Burlington, Kansas 66839 Office of the Governor State of Kansas Topeka, Kansas 66612 u torney General 1st Floor - The Statehouse Topeka, Kansas 66612 Chairman, Coffey County Commission Coffey County Courthouse Burlington, Kansas 66839 l

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Enclosure l

REQUEST FOR ADDITIONAL INFORMATION REGARDING COLD OVERPRESSURE MITIGATION SYSTEM (COMS)

WOLF CREEK UNIT 1 REACTOR SYSTEMS BRANCH

1. Describe the thermal-hydraulic analysis performed'in the PORV setpoint study to prevent a potential violation of. allowable P/T limits during plant heatup and cooldown. Including the following:

a. Major assumptions used in the current analysis as well as the analysis presented in the FSAR.

- b. Brief discussion of.the methodology / computer code used in the analysis,

c. Transient RCS pressure'at various PORY setpoints

d. Comparison of the peak RCS transient pressure with the all' owable P/T limits to confirm that the Appendix G P/T limits will not be violated.

2. ItisindicatedintheproposedTechnicalSpecification-(TS)thatthe

- PORV.setpoints are higher than the correspondent Appendix G P/T limits during the low temperature ( < 150*F) range. Provide , justification of why this apparent violation oT the regulations.is acceptable. Modify the PORV setpoints and reduce the allowable plant heatup and cooldown rate to assure that the Appendix G P/T limits are protected by the COMS at Wolf

- Creek Unit 1.

3. Discuss the TS restr'-tions regarding the availabilities of ECCS pumps and conditions which permit startup of a reactor coolant pump in order to support the assumptions made in the safety analysis, m--_a--u- .--------_.mu---_---_