IR 05000338/1979021
| ML19246B440 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/15/1979 |
| From: | Dyer J, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19246B422 | List: |
| References | |
| 50-338-79-21, NUDOCS 7907130490 | |
| Download: ML19246B440 (6) | |
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UNITED ST ATES
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Report No. 50-338/79-21 Licensee: Virginia Elect ric Power Company Richmond, Virginia 23261 Facility Name: North Anna Unit 1 Docket No. 50-338 License No. NPF-4 Inspection at North Anna Site near Mineral, Virginia Inspector:
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,yh J. A. Dye r /
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[1 R. D. Martin', Section Chief, ROSS Branch Date Signed SLTIARY Inspection on April 30-May 3, 1979 Areas Inspected
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This routine, unannounced inspection involved 27 inspector-hours onsite in the areas of Licensee Event Report review and review of valve, breaker, and switch alignment procedures against current flow and one line diagrams.
R sults
Of the two areas inspected, no apparent items of noncompliance or deviations were it:ntified in one area; one apparent item of noncompliance was found in (Infraction - Failure to establish, implement and maintain written one area procedures for the emergency diesel lube oil and cooling water systems - paragraph 6c).
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DETAILS 1.
Persons Contacted Licensee Employees
- W. Cartwright, Station Manager
- S. Harvey, Operating Supervisor
- W. Madison, NRC Coordinator
- J. Mosticone, Operations Coordinator
- E. Smith, Jr., Superintendent, Technical Services NRC Resident Inspector
- F. S. Kidd
- Attended exit 'nterview 2.
Exit Interview The inspection scope and findings were summarized on May 3,1979, with those persons indicated in Paragraph I above. The generic review of Licensee Event Reports (LER), as discussed in the Nuclear Power Station Quality Assurance Manual (NPSQAM) Section 16, item 6.2.2 was discussed.
The inspector pointed out that reviews for generic implications must be conducted and documented.
The licensee. committed to perform generic reviews in the Station Nuclear Safety and Operation Cocuaittee meetings on all LER's submitted subsequent to May 3, 1979. The inspector stated that all LER's submitted prior to May 3, 1979 must also be reviewed for generic implications. The licensee acknowledged the inspectors comment.
The inspector stated that he would contact the licensee concerning the time frame in which all LER's submitted prior to May 3,1979 must be reviewed af ter a review of this item with Region II management personnel.
With regard to the item of noncompliance discussed in paragraph 6.C, the licensee stated that written procedures for the emergency diesel lube oil and cooling water systems would be written and implemented as soon as practicable.
Subsequent to the inspection, the inspector contacted the licensee by
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telephone on May 9, 1979, concerning the review of all LERs, submitted prior to May 3, 1979, for generic implications. The licensee stated that these LERs vould be reviewed by a subcommittee. The results of the subcommittee will be reviewed by the Station Nuclear Safety and Operating
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Committee and a report issued addressing those LERs with generic in: plica-
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tions and the corrective action taken.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in paragraph 5.b.
5.
Review of Licensee Event Reports a.
The following 30 day LERs were reviewed to determine whether the reporting requirements were met, the report adequately assessed the event, identified the cause and corrective action was appropriate:
(1) LER 79-26, dated April 4,1979 (2) LER 7-29, dated April 16, 1979 (3) LER 79-30, dated April 4,1979 (4) LER 79 32, dated April 10, 1979 (5) LER 79-40, dated April 19, 1979 The inspector stated that LERs 79-30 and 79-40 did not clearly describe the Probable Consequences of Occurrence.
The licensee stated that supplemental reports would be submitted to clarify this item (0 pen Item 338/79-21-01).
b.
The inspector stated that the generic implications of all LERs have not been addressed as required by NPSQAM Section 16, item 6.2.2 and described in NUREG 016 (Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File).
Unresolved Item: All LERs submitted prior to and subsequent to May 3, 1979 must be reviewed for generic implications as described above (338/
79-21-02). (See also item 2 of this report).
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No items of noncompliance were identified.
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Followup to IE Bulletins 79-06,79-06A and 79-06A Revision 1 a.
In conjunction with the resident inspector, valve, breaker and switch alignment procedures for all engineered safety features (ESF) identified in section 6 of the FSAR were compared against current flow diagrams and single line diagrams to verify the adequacy of alignment procedures. The following table indicates the systems, operating procedures, checklists and drawings reviewed by the inspectors as of 1530 May 3,1979:
ESF LINEUP D' VIEWS OPEP\\ TING SYSTEM PROCEDURE CHECKLIST DRAWINGS COMENTS Emergency 6.1 (1-16-78)
Diesel 6.2 (1-16-78)
Generator 53.2 (10-3-78)
53.2A (10-30-78)
FB-35A 46.4 (10-30-78)
46.4A (10-30-78)
FM-107A ECCS Low Head SI 7.1 (10-30-78)
7.1A (10-30-78)
FM 96A-96B High Head SI 7.2 (10-30-78)
7.2A (10-30-78)
FM 96A-96B Accumulators 7.3 (10-30-78)
7.3A (10-30-78)
FM 96A-96B Quench Spray 7.4 (10-30-78)
7.4A (1-30-78)
FM 91A Outside Recirc Spray 7.5 (1-30-78)
7.5A (10-30-78)
FM 91A Inside Recire Spray 7.5 (10-30-78)
7 5A (10-30-78)
FM 91A Refueling Water Storage Tank 7.7
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-4-OPEEATING SYSTEM PROCEDURE
_ CHECKLIST DRAWINGS COMENTS Quench Spray Chemical Addition 7.8 (10-30-78)
7.8A (10-30-7)
FM 91A Casing Cooling 7.10 (10-30-78)
7.10A (10-30-78)
FM 91B Chemical Volume 8.1 (10-30-78)
FM 95A,B,C Control 8.8 (8-1-77)
8A FM 95A, B, C Electrical 26.0 (1-30-78)
26A (10-30-78)
FE-1A,1B,1C,1D IE,1F,1G,1E Se rvice Service Water Vater 49.1 (10-30-78)
49.1A(10-30-78)
FM 78A,78B,78C to charging pumps, RSRx Penetration Cooling Containment Hydrogen Recombiner 63.1(2-5-79)
63A (10-30-78)
FM 106A Control Room 21.9 (10-30-78)
21.6A (10-30-78)
FB 23A,34F, Still Working Ventilation 21.7 (12--78)
21.9A (10-30-78)
40A,B,44B,C,E at 1530 5/3/79 Auxiliary Feedwater 31.2 (10-30-78)
31.2A (10-30-78)
FM 74A-10 Still Working at 1530 5/3/79 Startup 1.1 (7-31-78)
To Mode 5 Procaderes 1.2 (6-26-78)
Mode 5 with bubble 1.3 (12-6-77)
To Mode 4 1.4 (6-26-78)
To Mode 3 Pre-Critical 1-0P-1A(10-6-76)
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Checklist 1-0P-1E(10-9-78)
b.
A list of inspector comm'ents were given to a licensee representative.
,,e The licensee stated that 1-0P-1A (Pre-critical checklist) was being revised to rr:flect the inspectors comments concerning valve identifi-
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cations and that drawing changes requests would be submitted where required. The inspector will review the changes to 1-0P-1A during a subsequent inspection (Open Item 338/79-21-03).
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-5-One apparent item of noncompliance was identified by the inspectors.
c.
Contrary to Technical Specification 6.8.1 written procedures have not been established, implemented, and maintained for the emergency diesel generator lube oil and cooling water systems (338/79-21-04).
For additional comments on the review of ESF systems see also the resident inspector's report 338/79-20.
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