IR 05000338/1978036
| ML19274D098 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 11/22/1978 |
| From: | Dyer J, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19274D097 | List: |
| References | |
| 50-338-78-36, 50-399-78-29, NUDOCS 7901090419 | |
| Download: ML19274D098 (5) | |
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Repott Nos.: 50-338/78-36 and 50-339/78-29 Docket Nos.:
50-338 and 50-339 License Nos.: NPF-4 and CPPR-78 Licensee: Virginia Electric Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Power Station Inspection at: North Anna Unit Nos. I and 2 Inspection conducted: October 24-27, 1978 Inspector:
J. A. Dyer Reviewed by:
7ttal N/7 2/77 R. D. Martin, Chief Date'
Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on October 24-27, 1978 (Report Nos. 50-338/78-36 and 50-339/78-29)
Areas Inspected:
Routine unannounced inspection concerning review of pre-operational test procedures and a tour of Unit No. 2 facilities. This inspection involved 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> onsite by one hTC inspector.
Results: Of the areas inspected no items of noncompliance were identified.
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RII Rpt. Nos. 50-338/78-36-1-and 50-339/78-29 DETAILS Prepared by:Nkd1
////f/7e GJ'. A. Dyep, Reactor Inspector Dat'e -
Nuclear Yupport Section No. 1 Reactor Operations and Nuclear Support Branch Dates of Inspection-ctober 24-27, 1978 Reviewed by:
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R. D Martin, Chief
' Da t'e Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted a.
Virginia Electric Power Company
- W. R. Cartwright, Station Manager I. B. Ferrer, Assistant Engineer
- S. Harvey, Acting Operations Supervisor '
G. A. Kann, Engineer D. G. McLain, Engineering Supervisor T. J. Schrenckenghost, Engineering Technician
- E.
R. Smith, Supervisor, Engineering Services T. J. Wilson, Engineer
- D. C. Woods, Senior Engineering Technician, NRC Coordinator b.
Stone and Webster R. J. Daly, Lead Advisory Engineer W. L. Lehmbeck, Assistant Lead Advisory Engineer c.
Westinghouse Electric Corporation O. E. Painter, Site Manager d.
Nuclear Regulatory Commission
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- M. S. Kidd, Resident Inspector
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings Not applicable.
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RII Rpt. Nos. 50-338/78-36-2-and 50-339/78-29 3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations. One unresolved item disclosed during the inspection are discussed in paragraph 5.b.3 of this report.
4.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on October 27, 1978.
The inspector stated that it appeared that the knowledge gained during the conduct of Unit No. I preoperational tests was not being utilized in the preparation of the Unit No. 2 preoperational test procedures.
Specific examples were identified by the inspector.
A licensee manage ment representative stated that the critiques and chronological logs for Unit No. I preoperational tests would be reviewed to determine what information could be utilized in the Unit No. 2 preoperational testr.
The inspector stated that one unresolved item was identified con-cerning the time interval between the preservice testing and inservice surveillance testing of safety and relief valves as described in IWV-3100 and IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code.
Licensee management representatives acknowledged the inspectors comments.
They stated that they felt they were conforming to their technical specifications in regards to the preservice and inservice testing of safety and relief valves. The inspector stated that this area of concern would be discussed with Region II management personnel.
Subsequent to the exit interview, the inspector contacted a licensee management representative by telephone on October 31, 1978 and informed him that the unresolved item on Unit No. I concerning the time interval between the preservice testing and inservice testing of safety and relief valves (paragraph I.5.b.3) was being forwarded to IE headquarters for review.
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All items presented in the following paragraphs were discussed.
5.
Review of Preoperational Test Procedures Preoperational tests were reviewed for conformance to Regulatory Guides 1.68 and 1.79, FSAR Table 14.1-1 FSAR Sections 3.9, 5.5.4., 5.5.6, 6.3.2, 6.3.4, 7.6.1.2, 8.3.1, 9.5.4, 10.3.2, 10.4.3 and Section XI of the ASME Cod.
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RII Rpt. Nos. 50-338/78-36-3-
50-339/78-29
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No discrepancies were noted during review of the following a.
procedures:
(1) 2PO-36.1: Safety Injection System Functional Test Breakers and Valves. Approved June 28, 1978.
(2) 2PO-36.2: Safety Injection System Functional Test Passive Systems (Accumulators). Approved May 31, 1978.
< (3)
2P0-39.2: Residual Heat Removal System Heat Removal Capability Test. Approved May 13, 1978.
(4)
2PO-50: RTD Sypass Flow Verification Prior to Core Loading.
Approved March 30, 1978.
(5) 2P0-52.2: Pressurizer Relief Tank Test During Hot Functional Testing. Approved September 18, 1978.
(6) 2P0-33:
Incore Thermocouple and RTD Cross Calibration.
Approved March 30, 1978.
(7) 2PO-56: Main Steam Decay Heat Release and Atmnspheric Dump Valves. Approved April 19, 1978.
(8) 2P0-57: Main Steam Safety Valve Setpoint Verification.
Approved April 19, 1978.
(9) 2P0-58.2: Main Steam Line Trys Valve Test at Hot Plant Conditions. Approved September 18, 1978.
(10) 2P0-60: Steam Generator Auxiliary Feedwater Pumps.
Approved June 21, 1978.
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Discrepancies were noted during review of the following procedures which will require resolution prior to the implementation of these procedures:
(1) 2PO-1: Emergency Power System. Approved April 19, 1978.
(a) The diesel lube oil system requires testing during full load operation of the diesels,. (Outstanding Item 78-29-01)
(b) The diesel cooling syrtems require testing during full load operation of the diesel. (Outstanding Item 78-29-02)
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RII Rpt. Nos. 50-338/78-36-4-
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and 50-339/78-29 (c) The diesel auxiliaries require preservice inspection per Section XI of the ASME Code. (Outstanding Item 78-29-03)
(d) The flow paths from all fuel oil sources to the diesel fuel oil pumps requires verification. (Outstanding Item 78-29-04)
(e) The diesel start capability from all stations requires verification. (Outstanding Item 78-29-05 )
(f) Valve lineup required for lube oil and cooling water system. (Outstanding Item '8-29-06)
(2) 2PO 36.4: Safety Injection System Hot Functional Testing.
Approved July 7, 1978.
(a) More definitive acceptance required on flow time to insure operability of check valves 92, 100, 106, 113 118 and 125. (Outstandine Item 78-29-07)
(b) Safety injection lines and accumulator discharge lines require filling and venting prior to commencing test.
K 2tstanding Item 78-29-08)
(c) Safety injection line flows will require th sttling to prevent robbing flow from charging and/or s al injection lines. (Outstanding Item 78-29-09 (3) 2PO-51:
Pressurizer Code Safety Valve Setpoint.
Approved May 22, 1978.
In conjunction with this test, the inspector again reviewed the test results for Unit No. 1; IPO-51 (IE Report 50-338/77-40, Details I.5.i).
The inspector identified a generic area of concern pertaining to the time period between preservice tests and inservice surveillance testing on safety and relief valves as described in Article IWV-3100 and IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code 1974 addition and addenda through summer 1975. This is designated as (Unresolved Item 338/78-36-01 for Unit No. D and Outstanding Item 339/78-29-10 for Unit No. 2.
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6.
Facility Tour The inspector toured various areas in Unit No. 2 to observe preparation for hot functional testing. No discrepancies were noted by the inspector.