ML16341E255
| ML16341E255 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/12/1987 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341E254 | List: |
| References | |
| 50-275-87-13, 50-323-87-12, NUDOCS 8706080087 | |
| Download: ML16341E255 (4) | |
Text
~Aendix A Notice of Violation Pac ific Gas andE 1 ectri c Company Diablo Canyon Nuclear Power Plant Docket Nos.
50-275 and 50-323 License Nos.
DPR-80 and DPR-82 During an NRC inspection conducted on March 15 through April 25, 1987 violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1987), the violations are listed below:
A.
10 CFR 50, Appendix B, Criter'ion XVI "Corrective Action" states in part that "Measures shall be established to assure that conditions adverse quality such as...deficiencies...and nonconformances are promptly identified and corrected."
Contrary to the above, on March 17, 1987 residual heat removal (RHR) crosstie valve 8716B on Unit 2 was closed for a period of twenty-eight hours for maintenance on the valve.
In September 1986, the Onsite Safety Review Group (OSRG) obtained information from NRC morning reports about the detrimental effects of closing SI and RHR crosstie valves.
During October 1986, the OSRG obtained additional information on this subject from the NRC and the D.
C.
Cook and Trojan Nuclear plants.
On October 30, 1986 the Onsite Safety Review Group issued Action Request A0042404 identifying the consequences of closing an RHR crosstie valve, and shortly thereafter discussed the consequences with plant management.
On January 6,
1987 IE Information Notice No. 87-01 "RHR Valve Misalignment Causes Degradation of ECCS in PWRs" was issued.
As of March 17, 1987, action had not been taken to restrict operation of the cross tie valve.
B.
This is a Severity Level IV Violation (Supplement I).
Facility Technical Specification 3.3. 1, Table 3.3-1, Item 16 specifies that the minimum number of operable channels for reactor trip on reactor coolant pump underfrequency is two per bus, with the provisions of Action Statement 6 applicable.
Action Statement 6 specifies that with the number of operable channels one less than the total number of channels, power operation may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the minimum channels operable requirement is met.
Contrary to the above, on April 19, 1987, one underfrequency channel on Unit 1 was not tripped within six hours of the discovery of its inoperability.
At approximately 1123 hours0.013 days <br />0.312 hours <br />0.00186 weeks <br />4.273015e-4 months <br /> I8C technicians, performing a
routine surveillance test on reactor coolant pumps Bus E underfrequency relays, put relay 81VER3 in its normal position after discovering at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> that it was inoperable.
The channel was not placed in a tripped condition until 0206 hours0.00238 days <br />0.0572 hours <br />3.406085e-4 weeks <br />7.8383e-5 months <br /> on April 20, 1987.
This is a Severity Level IV Violation (Supplement I).
8706080087 870512 PDR ADQCK 05000275 8
C.
Facility Technical Specification 6.8.1 states that:
"Written procedures shall be established, implemented and maintained covering applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, specifies procedures for "Authorities and Responsibilities for Safe Operation and Shutdown."
In partial implementation of this requirement, Nuclear Plant Administrative Procedure A-103, "Control Room Access," specifies that "Potentially distracting activities in the control room
. are prohibited."
Contrary to the above, on April 20, 1987, and for some time previous and
- after, an unused Unit 2 alarm in the control room was frequently being activated.
The alarm was not being used to monitor any actual plant parameter and.was distracting to control room personnel.
Apparently, as a result of the annoyance to personnel, inappropriate words were put on the alarm window which is another form of distraction.
Specifically, on one occasion, the words, "EAT AT JOE'S,"
showed when the alarm was lighted; on another occasion, the words, "PATRONIZE BOB'S BEANERY," were shown.
This is a Severity Level IV Violation (Supplement I).
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Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspector, Mr. P.
P. Narbut, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a
"Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation if admitted, (2) the corrective steps that have been taken and the results achieved; (3) the corrective steps that will be taken to avoid violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be. proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION Dated at Walnut Creek, California AN 1.2 lggy Dennis F. Ksrsc, Director Division of Reactor Safety and projects