IR 05000369/1985038
| ML20214G095 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/13/1986 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8611250557 | |
| Download: ML20214G095 (3) | |
Text
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November 13, 1986 Docket Nos. 50-369, 50-370 License Nos. NPF-9, NPF-17 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT: CONFIRMATION OF MEETING ARRANGEMENTS - MCGUIRE NUCLEAR STATION DOCKET N05. 50-369 AND 50-370 This confirms a telephone conversation between Mr. H. Tucker of Duke Power Company and Mr. R. Walker of my staff on November 12, 1986, concerning an
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Enforcement Conference to be conducted at the Region II office on December 8, 1986, at 1:00 p.m.
We requested this meeting to discuss our findings relative to operability concerns that were raised over the past operation of the nuclear service water system (RN) at the McGuire Nuclear Station.
These concerns were stated in the Region II inspection report Nos. 50-369/85-38 and 50-370/85-39.
The specific issues of concern which should be addressed at the conference appear in the enclosed Enforcement Conference agenda.
Should you have any questions regarding these arrangements, we will be pleased to discuss them.
Sincerely, (original signed by M. Ernst)
J. Nelson Grace Regional Administrator Enclosure:
Proposed Meeting Agenda cc w/ encl:
'T. L. McConnell, Station Manager
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ENCLOSURE PROPOSED MEETING AGENDA DECEMBER 8, 1986 AT 1:00 P.M.
I.
Opening Remarks J. Nelson Grace II.
Issues of Concern R. D. Walker Duke Power Representatives A.
Discuss the January 27, 1986, event which resulted in the cavitation of the RN pumps and resultant RN system low flow condition.
What bearing did this event have on past system operability?
B.
Discuss RN system preoperational testing.
1.
Why the McGuire Units 1 and 2 RN systems were not tested in a design basis accident configuration prior to January 27, 19867
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2.
Why were preoperational RN component throttle settings incorrectly translated to operating procedures?
3.
Why preoperational tests did not verify requisite RN flow to Units 1 and 2 control room air conditioners?
C.
Discuss the 10 CFR 50.59 evaluation which permitted the cross-connecting of RN system trains 1A and 2A in early October 1985.
How did that evaluation meet the criteria of 10 CFR 50.59?
D.
Discuss why Duke Power Company did not perform a formal engineering evaluation of the December 17, 1985, RN flow test results until January 1986?
E.
Discuss the quarterly 1A containment spray heat exchanger differential pressure test performed on October 7, 1985.
1.
What was the significance of the as-found RN flow of 800 gpm relative to past 1A containment spray heat exchanger operability?
2.
What was the significance of station's inability to achieve a 5000 gpm test flow?
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Enclosure
3.
Why the governing procedure, PT/1/A/4403/04, lacked qualitative or quantitative acceptance criteria?
F.
In retrospect considering all the information obtained from RN system testing, discuss the overall operability of the RN system prior to the implementation of corrective actions.
G.
Discuss the lessons learned, the current status of the station's RN systems, and future corrective actions.
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