ML20151E936
| ML20151E936 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/13/1988 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-004, IEB-88-4, NUDOCS 8807260267 | |
| Download: ML20151E936 (4) | |
Text
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'Af resephone (412) 393-6000
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July 13, 1988 Shippingport, PA 15077-(004 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 NRC Bulletin No. 88-04 Gentlemen:
We have reviewed NRC Bulletin 88-04, "Potential Safety-Related Pump Loss" for applicability to BVPS-1 and -2.
We have reviewed all BVPS-1 and
-2 safety related pumps in respect to the miniflow pump concerns identified in this bulletin.
All of our pumps are censidered adequately protected for these corcerns except as noted in the enclosed.
This open item is under going calculatory evaluation and the resulting response will be provided within 30 days.
If there are any questions concerning this response, please contact my office.
Very ruly yourn, 1
J.
J.
Care Exe utive Vice President of Operations Enclosure ces Mr. J. Beall, Sr. Resident Insoector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Project Manager f65 f 8807260267 800713 PDR ADOCK 05000334 I l c
G PDC
~
a.
.4 COMMONWEALTH OF PENNSYLVANIA)
)
SS:
COUNTY OF BS8E23R 4 u.gdNEA/ / )
On this
/J day of
('ul f
- 1988, before me, 2),me c2) v. SNANNoN',
a Notary Public in and for said Commonwealth and
- County, personally appeared J. J. Carey, who being duly sworn, deposed, and said that (1) he is Executive Vice President of Operations for Duquesne
- Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
Y : : = -:.- -J DONALD W. SHANNON. NOTARY PU8 tlc PITISBURGH, All[CHINY COUNTY MY COMMIS$10N EIPit!5 JUNE 7, IMI 1
Member, Pennsylvania Assocation of Notaries 4
.... ~
BVPS-1/-1 MRC BULLETIN 88-04 RESPONSE NRC Bulletin 88-04 requested DLC to evaluate BVPS-1 and -2 safety related pumps in regards to two centrifugal pump miniflow design concerns.
The first concern involves the potential for the dead-heading of one or more pumps in safecy-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.
A second coneern-is whether or not the installed miniflow capacity is adequate for even a single pump in operation.
In resolving these pump
- concerns, DLC has developed a list of BVPS-1 and
-2 centrifugal pumps in non-compressible fluid systems that:
(1) use miniflow lines, and/or (2) are in piping arrangements that could cause a possible pump-to-pump interaction.
Based on this
- list, evaluations were performed on BVPS-1 and -2 pumps to determine if any pumps were adversely affected by either of these two pump Concerns.
With the exceptions identified below, all of the SVPS-1 and -2 pumps are found to be adequately protected for the noted miniflow pump concerns.
As requested per NRC Bulletin 88-04, a written response to action item 4 is provided below:
(a)
All pumps identified as having a possible miniflow or i
pump-to-pump interaction during miniflow operation concerns have been evaluated with the below pumps and i
system concern affected.
RESPONSE
Except for BVPS-1 Reactor Plant Component Cooling Water Pumps (CCP)
(CCF-1A,-1B
& 1C), all BVPS-1 and -2 safety related pumps having a possible miniflow or pump-to-pump interaction during miniflow operations have been evaluated and found acceptable.
The BVPS-1 CCP3 are still being evaluated thru further calculations but the BVPS-1 history of these pumps indicates there should not be a
flow problem.
Evaluation on the CCPs will be provided within 30 days.
(b)
Based on the concern noted in (a)
- above, identify short-te*m and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations.
RESPONSE
Since BVPS-1 history of the CCPs have not indicated a
- problem, no short-term or long-term modifications will be implemented until the pump evaluation is completed.
Required modifications (if required) will be identified after completion of the pump evaluation within 30 days.
NRC BULLETIN 88-04
- RESPONSE (CONT'D)
Page 2 (c)
Identify the appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this bulletin.
RESPONSE
The appropriate schedule (if required) will be provided upon completion of the pump evaluation within 30 days.
(d)
Justification for continued-operation based on the above concern is evaluatad below particularly with regard to 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".
RESPONSE
History of BVPS-1 CCPs indicate these pumps do not have a flow problem and appear to be sufficient to support emergency conditions.
Also, these CCPs are not required to support ECCS operations.
Therefore, continued operation of BVPS-1 and -2 is considered justified.
-