ML20151F043
| ML20151F043 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 07/11/1988 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-004, IEB-88-4, TAC-69898, TAC-69899, NUDOCS 8807260316 | |
| Download: ML20151F043 (5) | |
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11ALB. TUCKER (7 % 07 N 538 TELEPHONE voca esserner, avotaan reoou crion July 11, 1988 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555
Subject:
McGuire Nuclear Station Catawba Nuclear Station Oconee Nuclear Station Docket Nos. 50-369, -370; 50-413, -414; and 50-269, -2 70, -287 NRC Bulletin No. 88-04 Potential Safety-Related Pump Loss Gentlemen:
Mr.
C.E.
Rossi's (NRC/0NRR) May 5, 1988 letter (Bulletin 88-04) concerned Potential Safety-Related Pump Loss.
The purpose of this bulletin was to request investigation and correction, as applicable, of two miniflow design concerns.
The first concern involves the potential for the dead-heading of one or more pumps in safety-related systems that have a miniflow line common to two or more pumps or other piping configurations that do not preclude pump-to-pump interaction during miniflow operation.
'Ihe second is whether or not the installed miniflow capacity is adequate for even a single pump in operation.
The bulletin requested (Action No. 4) that a report be submitted within 60 days of receipt of the bulletin that (a) summarizes the problems and the systems affected, (b) identified the short-term and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations, (c) identifies an appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this lulletin, and _ (d) provides justification for continued operation particularly with regard the General Design criterion 35 of Appendix A to Title 10 of the Code of Federal Regulations (10 CFR 50),
"Emergency Core Cooling" and 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling System for Light Water Nuclear Power Reactors." While Duke Power Company's review of the bulletin is well underway, we are not able to provide the requested response on individual pumps at this time.
8807260316 880711 PDR ADOCK 0"A00369
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PDC l
J Document Control Desk July 13, 1988 Page 2 Activities currently underway with respect to the b'ulletin include:
o Identification of all active safety-related pumps.
(All applicable pumps are listed on the Attachm'ents - Attachment 1 (ONS), Attachment 2 (NWS/CNS)),
o Evaluation of design information related to pump dead-heading and pump minimum flow, o
Collection and evaluation of test and maintenance data.
o Requesting manufacturer input on minimum flow requirements.
(All manufacturers have been contacted and their schedules are being received).
A response -to the bulletin is not possible at this time since responses have not yet been received from pump manufacturers regarding minimum flow requirements (Reference the attachments for the involved pumps and manufacturers).
Af ter receiving manufacturer information, each pump will be evaluated for any needed procedural or hardware changes, which could involve the need for field testing and runs on analytical models.
It is expected that the receipt of manufacturer information and an evaluation of the information can be completed by August 31, 1988.
However, completion of needed testing, analytical models and scheduling of needed procedural or hardware changes may not be completed by August 31, 1988.
Therefore, Duke will provide a status of progress on August 31, 1988, including any available final bulletin responses for specific pumps, i
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge.
Should there be any questions concerning this macter or if additional information is required, please advise.
Very truly yours,
/$h V ssacs Hal B. Tucker PBN/IOO/ bhp i
Attachmenta i
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r Documbnt Control Desk July!13, 1988 Page 3 xc: w/ attachments Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station Mr. P.K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. P.H.-Skinner NRC Resident Inspector Oconee Nuclear Station Mr. Darl Hood Office of Nuclear Reactor Regulation U.S. Nuclear Reg 61atory Commission Washington, DC '20555 Dr. K.N. Jabbour Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 9
Ms. Helen Pastis Office Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
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Oconee Safety-Related (Active) Pumps Pumps Manufacturer 1.
Low Pressure Injection (LPI) 1A,lB,2A,2B,3A,aB Ingersoll-Rand
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2.
High Pressure Injection (HPI) 1A,lB,1C,2A,2B,2C, Ingersoll-Rand 3A,3B,3C 3.
Reactor Building Spray (RBS).
lA,lB,2A,2B,3A,3B Ingersoll-Rand 4.
Motor Driven Emergency Feedwater lA,lB,2A,2B,3A,3B Bingham (MDEFDW) 5.
Turbine Driven Emergency lA,2A,3A Bingham Feedwater-(TDEFDW) l 6.
Auxiliary Service Water (ASW) 1A Ingersoll-Rand 7.
Low Pressure Service Water lA,lB,1C,3A,3B Ingersoll-Ra'i (LPSW) 8.
SSF Auxiliary Service Water P2 Bingham (SSFASW) 9.
SSF HVAC Cooling Water 1,2 Ingersoll-Rand (SSFHVAC)
- 10. SSF Diesel Engine Water 1
Ingersdll-Rand Jacket (SSFDEWS) i l
McGuire/ Catawba Safety Related (Active) Pumps v
Pumps Manufacturer 1.
Centrifugal Charging (NV) 1A',lB,2A,2B Pacific 2.
Boric' Acid Transfer (NV) 1A,lB,2A,2B Crane-Chempump-3.
Residual Heat Removal (ND) 1A,lB,2A,2B Ingersoll-Rand 4.
Safety Injection (NZ) 1A,lB,2A,2B Pacific 5.
Containment Spray (NS) 1A,lB,2A,2B Ingersoll-Rand (MNS)
Bingham-(CNS) 6.
Motor Driven Auxiliary 1A,lB,2A,2B Bingham Feedwater (CA) 7.
Turbine Driven Auxiliary 1,2 Bingham.
Feedwater (CA) 8.
Component Cooling (KC) 1Al,lA2,lB1, B&W Canada,Ltd.
1B2,2A1,2A2, (MNS) 2B1,2B2 Goulds(CNS) 9.
Nuclear Service Water (RN) 1A,lB,2A,2B Bingham l'0. Control Area Chilled Water 1,2 Goulds (YC) l
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