IR 05000338/1978032
| ML19263B337 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/20/1978 |
| From: | Robert Lewis, Webster E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B317 | List: |
| References | |
| 50-338-78-32, NUDOCS 7901180059 | |
| Download: ML19263B337 (8) | |
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Report No.
50-338/78-32 Docket No.-
50-338 License No.
NPF-4 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Power Station, Unit 1 Inspection at: North Anna Power Station, Mineral, Virginia Inspection Conducted: October 16-19, 1978 Inspector:
E. H. Webster
[.d.
//b/M Approved by:
Date R. C. Lewis, Chief Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on October 16-19, 1978 (Report No. 50-338/78-32)
Areas Inspected: Routine, unannounced inspection of licensee event reports, licensee followup on open items, and controls on non-annunciated diesel generator alarms.
The inspection involved 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> onsite by one h7C inspector (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> involved conduct of a tour for h3C Office of the Secretary personnel).
Results:
Within the three areas inspected, no items of noncompliance or deviations were identified in two areas; one apparent deviation was identi-fied in one area (Failure to log emergency diesel component status as committed to in VEPCO correspondence to NRC (78-32-01) - Paragraph 6).
7901180ON
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RII Rpt. No. 50-338/78-32 I-1 t
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DETAliS I Prepared by:
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E. H. Webster, Reactor Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: October 16-19, 1978 E. c. b
///2e/71 Reviewed by:
R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted Virginia Electric and Power Company a.
- W. R. Cartwright, Station Manager
- J. D. Kellams, Operating Supervisor
- L. O. Goodrich, Supervisor, Mechanical Maintenance
- E. R. Smith, Supervisor, Engineering Services
- D. C. Woods, Senior Engineering Technician
- D. E. Thomas, Electrical Maintenance Coordinator
- E. W. Harrell, Engineering Supervisor G. M. Stokes, Fire Marshall F. C. White, Deputy Fire Marshall b.
U. S. Nuclear Regulatory Commission
- M. S. Kidd, Resident inspector
- Denotes those present at the exit interview.
2.
License Action on Previous Inspection Findings Not inspected.
3.
New Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. An unresolved item disclosed during this inspection is discussed in paragraph 5.b.(7).
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RIl Rpt. No. 50-338/78-32 1-2 4.
Management Interview The inspector met with W. R.
Cartwright and other licensee staff members (denoted in paragraph 1) at the conclusion of the inspection on October 19, 1978. The scope and findings of the inspection were summarized by the inspector.
The licensee agreed with the item of deviation.
5.
Review of Licensee Event Reports a.
Written Repo t Review The fe'.iowing thirty-day LERs were reviewed to determine whether repor:ing requirements had been met, the report assessed the event and identified the cause, and corrective action was appropriate:
(1) LER 78-39 dated June 9,1978 (2)
LER 78-41 dated June 27, 1978 (3)
LER 78-42 dated June 16, 1978 (4) LER 78-43 dated June 27, 1978 (5. ) LER 78-48 dated July 12, 1978 (6) LER 78-50 dated July 12, 1978 (7)
LER 78-54 dated July 12, 1978 (8)
LER 78-55 dated July 12, 1978 (9) LER 78-56 dated July 12, 1978 (10)
LER 78-57 dated July 12, 1978
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(11)
LER 78-58 dated July 28, 1978 (12)
LER 78-61 dated October 10, 1978 (13)
LER 78-64 dated August 10, 1978 (14)
LER 76-65 dated August 16, 1978 (15)
LER 78-66 dated September 7,1978
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RII Rpt. No. 50-338/78-32 I-3 (16) LER 78-67 dated August 10, 1978 (17)
LER 78-69 dated August 21, 1978 (18)
LER 78-72 dated September 7,1978 (19) LER 78-73 dated August 21, 1978 (20)
LER 78-76 dated September 7,1978 (21)
LER 78-77 dated September 7,1978 (22)
LER 78-18 dated September 13, 1978 (23)
LER 78-79 dated September 13, 1978 (24) LER 78-82 dated September 13, 1978 (25)
LER 78-86 dated September 22, 1978 (26)
LER 78-87 dated September 27, 1978 (27) LER 78-88 dated September 22, 1978 Except for the timeliness of these reports, which will be discussed below, no discrepancies were noted.
b.
Written Report Review and Followup Onsite In addition to performing a report review as defined in a. above, site followup was performed for these LERs to determine whether ccrrective action specified had been taken, the licensee had reviewed the event, whether it involved an unreviewed safety question or violation of regulations or whether a corrected LER had been submitted, if required:
(1)
LERs 78-59 dated July 28, 1978, 78-68 dated September 7, 1978, 78-71 dated August 21,1978, and 78-75 dated August 21, 1978. All four of these reports discussed separate occurrences of exceeding the Quadrant Power Tilt (QPT) limit of 1.02 because of difficulties with nuclear detector N44.
Log reviews and interviews with operators confirmed the drif t of the power range detector causing excore instrumentation to indicate a radial tilt of neutron flux. Documentation for the detector replacement, completed September 26, 1978, was reviewed and considered satisfactory.
Discussions with operators revealed that excore detector current values were
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Rll Rpt. Na. 50-338/78-32 I-4 rounding-off for use in PT-23 for calculation of QPT.
In one case, (LER 78-68) the QPT calculation had been found by the licensee technical staff to be above 1.02 af ter the initial calculation had determined the value of QPT to be 1.01 by rounded-off current values to two significant decimal places.
Licensee management is reviewing this area and plans to develop policy so that the technical staff and the operatort are consistent in mathematical calculations.
The inspector will followup on this item in subsequent inspections. (open item 78-32-05)
(2)
LERs 78-44 dated June 28, 1978, 78-45 dated June 28, 1978, and 78-81 dated September 13, 1978.
All three of these reports concerned s~parate occurrences of exceeding the 105 F maximum bulk ace. age containment temperature limit.
Although the cause for the temperature excursions reported were varied, the root problem involves the chilled water system design performance and reliability. Lic nsee manage-ment discussed proposed actions to increase both cooling capability and reliability of the chilled water system to further insure containment temperature control. The inspector had no further questions concerning corrective actions taken to this point but shall review chilled water system improve-ments in the future (open item 78-32-02).
(3)
LERs 78-70 dated August 21,1978, and 78-83 dated September 22, 1978.
Both reports concerned charging pump cubicle ambient temperature exceeding the license limits.
Since these events the auxiliary building ventilation system has been completed, tying all six charging pump motor exhausts together, thus reducing ambient temperatures in the running (Unit 1)
pump cubicles. The inspector had no further questions in this area.
(4) LERs 78-40 dated June 12,1978, and 78-84 dated September 22, 1978.
Both reports concerned valve stroke timing not being conducted per Technical Specification 4.6.3.1.1 following maintenance on a valve or valve control circuit.
Licensee management showed the inspector plans to incorporate the Technical Specification listing of valves requiring timing after maintenance (Technical Specification Table 3.6-1) into their generic mechanical valve maintenance procedures and agreed to do the seme for their generic electrical valve maintenance procedures.
This item remains open pending review of the revised procedures (open item 78-32-03).
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RII Rpt. No. 50-338/78-32 1-6 The above item is in noncompliance with Technical Specifications, Section 6.9.1.9 and is similar to an item of noncompliance identified in Inspection Report No. 78-21.
Whereas the above item was identified prior to the licensee's response to report 78-21, this item is reported as another axample of the noncom-pliance (infraction 78-21-01) identified in Inspection Report No.
78-21.
6.
Review of Diesel Generator Auto Start Functions The inspector reviewed the licensee design to insure emergency diesel generator capability to start on an emergency condition, as detailed in correspondence witt. Office of Nuclear Reactor Regulation (0NRR),
NRC.
In a letter, serial 323/053178 dated July 7, 1978, to ONRR, the licensee detailed two items which could cause the diesels to f ai] to respond to emergency start signals:
Air start manual isolation valves closed a.
b.
2ontrol room selector switch in " MANUAL-LOCAL" To insure operability of the diesels in light of this informatiog the licensee st.'ed in this letter that these items are checked every four hours and recorded in the diesel log by an operator.
Contrary to the commitment in the letter, the inspector found on October 19, 1978, that the affected valve and switch positions were checked every four hours but were not logged in any plant log. This item is a deviation (deviation 78-32-01).
7.
Followup on Previously Identified Open Items Administrative Controls of Flammable; in the Plant (item 78-25-02)
a.
This open item concerned administrative control by the fire marshall of flammables used in the plant.
The licensee has instituted an administrative control system utilizing a log and metallic signs which are controlled at all entry areas to the plant.
By this means all flammables entering the plant are identified by responsible person and job function. This item is close '
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RII Rpt. No. 50-338/78-32 I-7 b.
Coordination of Flammable Control With Stone and Webster Company (Item 78-25-03)
The flammable control program described above is applicable to Stone and Webster construction workers as well as licensee personnel. This action is to insure licensee control over all operating plant spaces. This item is closed.
Mobile Fire Extinguisher Inspection (Item 78-25-04)
c.
This open item concerned procedural coverage of surveillanca inspections on mobile fire extinguishers.
Licensee personnel have proposed new periodic test (PT) procedures to cover fire extinguishers attached to welding carts and in spares for use on welding carts.
This item remains open pending issuance of these new procedures.
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