ML20133D993

Notification of 850805 Meeting W/Util & B&W in Bethesda,Md to Discuss Proposed Exemption to GDC 4 for Reactor Coolant Pump Supports.Draft Agenda Encl

ML20133D993
Person / Time
Site:	Crystal River
Issue date:	07/30/1985
From:	Silver H Office of Nuclear Reactor Regulation
To:	Stolz J Office of Nuclear Reactor Regulation
References
NUDOCS 8508070540
Download: ML20133D993 (7)

Text

July 30,1985 I

-0!b Docket No. 50-302 MEMORANDlN FOR: ~ John F. Stolz, Chief, Operating Reactors Branch #4, DL

-FROM: 'Harley Silver, Project Manager, Operating Reactors Branch #4, DL.

SUBJECT:

FORTHCOMING MEETING WITH FLORIDA POWER CORPORATION REGARDING CRYSTAL RIVER UNIT 3-Time & Date: Monday, August 5, 1985 1:00pm Location: Phillips Building, P-114 Bethesda, Maryland

Purpose:

To discuss licensee's proposed exemption to GDC-4 for RCP s supports - see enclosed agenda and exemption request.

Requested

Participants:

NRC-WJohnston, RKlecker, KWichman, RBosnak, JShea, J0'Brien Licensee-KWilson, EDavidson, et al, ESimpson Other-B&W-FWalters, JTaylor W W 1f Harley Silver, Project Manager Operating Reactors Branch #4, DL

Enclosure:

As Stated cc w/ enclosure:

See next page OR :DL HSilver;cr 7Md85 8500070540 85073032

, DR ADOCK 050

_ DRAFT AGENDA EETING TO DISCUSS REQUEST FOR EXEMPTION FROM A PORTION OF 10 CFR. APPENDIX A. GENERAL DESIGN CRITERIA 4 PHILLIPS BUILDING, BETHESDA. 10.

AUGUST 5,1985 1:00 1. INTRODUCTION E.C. SIMPSON ,

A. FPC Attendees B. Purpose of Meeting C. Discussion of Agenda 1:05  !!. BACKGROUND K.R. WILSON A. NRC Piping Review Committee B. B&W Generic Submittal of Oct. 7,1984 C. LBB Methodology as Applied to CR-3 D. FPC Letter of Feb. I,1985 1:20  !!!. CURRENT PLANS OF FPC J.R. MASEDA A. Project Schedule to Support Refuel 6 B. Optimization Analysis

- Recent damping values

- Retention of stress margin

• C. Revised Schedule of Submittals 1:45 IV. INPUT FROM NRC A. Comments on FPC Letter of Feb. 1, 1985 B. Comments on Current Plan of FPC C. Scope and Format of Future FPC Submittals D. Schedule for NRC Review 2:00 Y. CONCLUSIONS E.C. SIMPSON m

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i l February 1,1985 3F0285-02 4

Mr. Harold R. Denton Office of Nuclear Reactor Regulation Attn: Document Control Desk U.S. Nuclear Regulatory Commission -

Washington, DC 20535

Subject:

Crystal River Unit 3 Docket No. 50-302 l Operating License No. DPR-72 i

REQUEST FOR EXEMPTION PROM A PORTION OF 10 CFR 50,. APPENDIX A, GENERAL DESIGN CRITERIA 4

Dear Mr. Denton:

Florida Power Corporation (FPC) hereby requests exemption from a portion of certain i

requirements of General Design Criteria 4 (10 CFR 50, Appendix A) pursuant to the provisions of 10 CFR 50.12(a). As indicated in Generic Letter 84-04, the staff has accepted the utilization of the leak-before-break concept on certain dockets as a means of obviating the need to install certain piping / equipment support systems. The attached Exemption Request utilizes such methodology to support the exclusion of dynamic LOCA loads from the RCS piping, which will allow us to reduce the number of large bore hydraulic snubbers restraining the reactor coolant pumps. . Attachment A summarizes this Exemption Request i and Attachment B provides the scheduled milestones necessary to support snubber restraint I

arrangement modifications in Refuel VI. Pursuant to 10 CFR 170, a submittal fee of $150 is attached.

FPC hereby requests a meeting among NRC, Babcock & Wilcox, and FPC representatives to '

clearly define NRC staff needs for information to support your approval of this request. Mr.

Ken Wilson (904) 795-3802 (Extension 4549) is the FPC contact to arrange such a meeting.

Sincerely, .

G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management j

PGH/feb o@h2 j \

P PDR g hC9 5 N GEN ERAL OFFICE 3201 Thirty fourth street south e P.O. Box 14042, st. Petersburg. Florida 33733 o 813-806-5151

. ATTACHMENT A EXEMPTION PROM A PORTION OF 10 CPR 50 APPENDIX A GENERAL DESIGN CRITERIA 4 As required by Generic Letter 84-04, Florida Power Corporation (FPC) requests exemption, pursuant to 10 CFR 30.12(a), from a portion of General Design Criteria 4 (GDC-4) for Crystal River Unit 3. Specifically, FPC requests exemption from that portion of GDC-4 which requires protection of the reactor coolant system (RCS) from the dynamic effects i (i.e., pipe whipping and discharging fluids) associated with a LOCA involving double-ended rupture of RCS piping.

SCOPE OF REOUEST:

Approval of this exemption will allow FPC to redesign the RCS pump restraint system in order to:

o Remove several large bore hydraulle snubbers currently restraining the reactor coolant pumps (up to 20 out of a total of 32). ,

o Replace other reactor coolant pump large bore snubbers with rigid restraints (4 restraints). - '

o Replace remaining reactor coolant pump large bore snubbers with smaller snubbers (8 smaller snubbers).

FPC must remove all large bore snubbers for rebuilding and testing due to service life

. considerations. Substantial Man Rem and dollar savings will be realized if these large bore j snubbers do not have to be reinstalled or can be replaced with rigid restraints or smaller snubbers. These savings will be discussed in more detail in the safety balance value-impact statement that is being prepared for submittal consistent with the attached tentative schedule.

Granting this exemption request would not affect:

o ECCS design basis.

o Reactor building and compartment design basis.

o Equipment Qualification basis.

o Engineered Safety Feature Systems response.

o Currently installed pipe whip restraints, jet impingement shields and small bore RCS snubbers.

JUSTIFICATION FOR REOUEST:

On September 7,1984, FPC, as a member of the B&W Owners Group, submitted BAW-1847,

" Leak Before Break Evaluation of Margins Against Full Break for RCS Primary Piping of B&W Designed NSS". This report provides the technical basis for determining that a double-ended guillotine break will not occur and that postulated flaws producing detectable leakage exhibit stable growth. The evaluation includes structural and fracture mechanics analyses using generic bounding data (loads and material properties) for all B&W Owners Group

. plants. The bounding loads and properties assumed are such that even with removal and/or replacement of the large bore snubbers, Crystal River Unit 3 is still bounded by the Generic Report. Additional justification will appear in the CR-3 plant-specific submittals shown in Attachment B.

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ATTACHMENT B TENTATIVE SCHEDULE Date of Action Action Item June 1,I!)S5 Crystal River Unit 3 Leak-Before-Break Evaluation of RCS Piping Submittal to NRC June 1,1985 Crystal River Unit 3 Safety Balance Value-Impact Statement Submittal to NRC To Be Determined RCS Leakage Detection System Capability Esaluation Submittal to NRC

. October 1,1985 NRC Approval of Exemption

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July 1986 Technical Specification Change Request Submittal to NRC -

October 1986 Refuel VI Begins October 1986 NRC Approval of Technical Specification Amendment e

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f STATE OF FLORIDA COUNTY OF PINELLAS G. R. Westafer states that he is the Manager, Nuclear Operations Licensing and Fuel Management for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

G. R. Westafer Manager, Nuclear //

Operations Licensing and Fuel Management Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 1st day of February,1985.

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fM4 Notary Public l h  ;

Y I Notary Public, State of Florida at Large, '

l My Commission Expires: November 19,1986 1

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MEETING NOTICE DISTRIBUTION OPERATING REACTORS BRANCH #4, DIVISION OF LICENSING Docket File NRC PDR L PDR ORBf4 Rdg Project Manager-HSilver JStolz Glainas BGrimes OELD GHolahan, ORAB HDenton ELJordan, IE -

ACRS-10 MSchaaf ~

NSIC PMorriette Receptionist Regional Administrator Region-II Resident Inspector, NRC Meeting

Participants:

WJohnston RKlecker KWichman RBosnak JShea J0'Brien

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