ML19254E394
| ML19254E394 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/23/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254E390 | List: |
| References | |
| 50-334-79-14, NUDOCS 7911010027 | |
| Download: ML19254E394 (2) | |
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APPENDIX A NOTICE OF VIOL 4 TION Duquesne Light Company Docket No. 50-334 Based on the results of an NRC inspection conducted June 5-8, 1979, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Facility License No. DPR-66, as indicated below. Item A is an infraction and Items B and C Gre deficiencies.
A.
Infraction Technical Spet. ~ ' cation 4.4.9.1.a states, "The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations."
Technical Specification 4.4.9.2 states, in part, "The Pressurizer temperatures shall be determined to be within the limits once per 30 minutes during system heatup or cooldown...."
Technical Specificatfor 6.8.1. states, in part, " Written procedures shall be established, implemented and maintained covering the activities referenced below.... Surveillance and test activities of safety-related equipment...."
Contrary to the above, it was observed that neither the heatup nor cooldown rates of the Pressurizer and Reactor Coolant System are determined every 30 minutes during heatup or coo ~down of these systems.
In addition, station operating procedures for operaticn of the Reactor Coolant System and Pressurizer, while specifying the correct heatup and cooldown rstes, do not provide instructions for determining whether these rates are within limits every 30 minutes during heatups or cooldowns.
B.
Deficiency Technical Specification 6.8.1 states, in part, " Written procedures shall be established, implemented and maintained covering the acti-vities referenced below....The applicable procedures recommended in Appendix 'A' of Regulatory Guide 1.33, November 1972...."
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Appendix A 2
Appendix A of Regulatory Guide 1.33, November 1972, states, in part, "The following are typical safety-related activities which should be covered by written procedures.... Procedure Adherence and Temporary Change Method...."
BVPS-0M 1.48.3.E.6, On-the-Spot Revisions, states, in part, "...the OMCN may be in effect for 7 days without the additional approval of the BVPS Superintendent (or alternate). After review by the Onsite Safety Committee (OSC) and approval by the BVPS Superintendent...the OMCN may remain in effect an additional 90 days.
If the OMCN has not been approved by the Superintendent within 7 days of the effective date, or the revision to the Chapter section has not been issued within 90 days, the change notice will be removed from the controlled copies."
Contrary to the above, the following deficiencies were noted during review of Station operating procedures:
In six instances, temporary changes which had expired were still posted to control copies of Station operating procedures.
In one instance, a temporary change was posted to a procedure, however, no change authorization sheet was present.
Jhis temporary change had been superceded by a revision which had failed to change that portion of the procedure.
In two instances, a temporary change was nnde to procedures without issuance of a temporary change at:horization.
On 77 separate occasions between March 2, 1979 and May 31, 1979, the wrong change to a daily log sheet had been used.
In one instance, an expired temporary change was posted to an opera-ting procedure although it had been superceded by a Temporary Opera-ting Procedure.
C.
Technical Specification 6.9.1.9 states, in part, "The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurecnce of the event...."
A Reactor Protection System or Engineered Safety Feature instrument settings, which are found to be less conservative than those established by the Technical Specifications but which do not prevent the fulfillment of the functional requirement of affected systems.
Contrary to the above, the failure of one Overtemperature Delta-T, Reactor Trip System instrument channel, which occurred on April 24, 1978, was not reported.
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