ML20024D766
| ML20024D766 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/20/1983 |
| From: | Larson C NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20024D762 | List: |
| References | |
| NUDOCS 8308080155 | |
| Download: ML20024D766 (3) | |
Text
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Northem States Power Company 414 Nicollet Mall Minneapoks. Minnesota 55401 Telephone (612) 330-5500 July 20, 1983 Mr. J.G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
Prairie Island Nuclear Generating Plants Docket No. 50-282, License No. DPR-42 and Docket No. 50-306, License No. DPR-60.
In response to your letter dated June 20, 1983, which transmitted Inspection Report No. 50-282/83-07 (DPRP); 50-306/83-07 (DPRP), the following information is provided.
Violation No. 1 Technical Specification 4.1.A states that calibration, testing and checking instrumentation channels and testing of logic channels shall be performed as specified in Table T.S. 4.1-1.
Table T.S.
4.1-1.35.b requires a daily check of Post Accident Monitoring Radiation Instruments.
Table T.S. 4.1-1.38 and 39 requires a monthly functional test of 4KV safeguards buses.
Contrary to the above:
a.
During the period April 4-11, 1983, the licensee did not perform a daily check of the main steam line radiation
- monitors, b.
During the period of January 5 - February 28, 1983, the re-quired monthly functional test for the 4KV safeguards buses was not performed.
This is a Severity Level V violation (Supplement I).
8309080155 830002 gDRADOCK05000 JQ g y g
r July 20, 1983 Page 2 J.G. Keppler
Response
a.
The daily checks had not been made because a license amendment containing the new surveillance requirements had not had timely distribution in the plant. Surveillance procedures were changed to include the daily checks. Administrative controls for the handling of license amendments in the plant have been tightened. This event was reported as R0 83-007/03L-0. Full compliance has been achieved.
b.
The test was missed because of personnel oversight. The error was discovered during routine review of the surveillance program. Men discovered, the test was performed and was acceptable, indicating the equipment was operable during the period.
Involved personnel have been reminded of the importance of close and timely review of the surveillance schedule. This event was reported as R0 83-003/03L-0.
Full compliance has been achieved.
Violation No. 2 Technical Specification 4.16.B, Fire Suppression Water System, states in part:
"j. Valves in flow paths supplying fire suppression water to safety-related structures, systems, and components shall be cycled every 12 months.
k.
Each valve (manual, power operated, or automatic) in the flow path for safety-related areas and areas posing a fire hazard to safety-related areas, shall be verified to be in its correct position every month and the method of securing the valve in its correct position shall be verified every month."
Contrary to the above, the licensee's surveillance test records indicate that:
a.
Valve No. FP-50-6, Deluge PA-1 Isolation for the Diesel Generator Room, was not cycled during the annual surveillance test performed on July 18, 1982.
b.
Valve No. 2FP-2-5, root valve for hose station No. 64, was not included in the monthly verification surveillance test procedure.
This is a Severity Level V violation (Supplement I).
July 20, 1983 Page 3 J.G. Keppler
Response
a.
The subject valve was not cycled during the annual test because one page of the procedure was missing.
Investigation showed the page was omitted during printing and assembly of the procedure. The valves on the missing page were later cycled satisfactorily. The missing page has been inserted into the control room blank copies. Full compliance has been achieved.
b.
Investigation showed that the valve was overlooked in preparing and reviewing the draft of the procedure.
Inspection of the valve showed it to be properly positioned, tagged and sealed. A revision to the surveillance test was initiated to add the valve and other descrip-tive information for easier location of each of the valves. Full compliance will be achieved by July 29, 1983.
Respectfully y s,
C. E. Lar Director Nuclear Generation CEL/sms cc: C Feierabend G Charnoff
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