ML20039G933
| ML20039G933 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/22/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039G932 | List: |
| References | |
| 50-267-81-26, NUDOCS 8201190319 | |
| Download: ML20039G933 (2) | |
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APPENDIX A NOTICE'0F VIOLATION Public Service Ccmpany Fort St. Vrain of Colorado Docket: 50-267/81-26 n.
c Based on the results of an NRC inspection conducted during the period cf November 1-30, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66745 Mctober 7,1980), the following violatiens were identified:
1.
Technical Specification LCO 4.6.ld) states in part that:
"The reactor shall not be operated at power unless the following conditions are satisfied:
"d) Both the diesel-generator sets are operable, including the following:
"4. 325 gallons of fuel in each day tank. One diesel generator set may be inoperable for up to 7 days (total for both) during any month provided the operability of the other diesel-generator set is demonstrated immediately as in a) above and all essential buses are operable...."
Contrary to the above, on October 20, 1981, and on October 21, 1981, Emergency Diesel Generator sets T( and 12, resoectively, were removed from service for maintenance without demonstrating the Operability of the alternate diesel-generator set immediately prior to their removal frem service.
This is a Severity Level III Violation.
(Supplement I.C.)
2.
Technical Specification 7.4.a, " Procedures, Administrative Controls,"
statas in part that, "... written procedures shall be established, implemented, and maintained...."
Administrative Procedure P-1, " Plant Operations," Issue 4, dated August 3,1981, Section 4.6.2 states in part as follows:
"EACH ASSIGNED
Also records in the proper RWP blocks:
a)
Film badge number b) Dosimeter number c)
Initial reading of dosimeter d) Time in...."
Contrary to the above, on November 16, 1981, a Health Physics Technician had failed to log into the radiation work cermit (RWP) control area and was not wearing a pocket dosimeter as required by the RWP.
This is a Severity Level V Violation.
(SuoplementIV.E.2) l l
8201190319 811222 PDR ADOCK 05000267 G
3.
Technical Specification 7.4.a', "P~rocedures, Administrative Controls,"
states in~part that, "..... written procedures 'shall be established,
- iirclemented,.land maintainec...."
A.
Administrative Procedure.P-2, " Equipment Clearances and Operations
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- 0eviations,"'
- Issue 4,' dated' June ~ 121 '1981;. Section 4.1. states,in;
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'partas followsi
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'"SNIFT'5UPERVISOR -
-- 13. ' Dire' cts' the' Reactor Operator o Tes' tore' '
t the equipment to normal conditions.
.."REACIOR OPERATOR 14.... Directs the Operations required to.
place: the equipment in-ssrvice :...
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- 16. Whert completed, sig'ns the form indicating the equipment is restored to normal conditions...."
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.Centrary to the -above, on November 3,1981, the PCRV Auxiliary Piping System equipment clearance.for' a modification performed on the helium penetration interspace for B-2-3 team generator mo-'ule was returned and the system returned to normal operation without ~laeeting the ' system's ' seismic requirements necessary to
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classify the system as operational.
9.
Controlled Work Permit 81-252 assigned to Change Notice 1427A, dated October 28, 1981, contained a step which stated, " Install pipe supports per CN 1427A SK-3, SK-4, SK-5."
This step has been classified as a Witness Point (WP) by the QA/QC department.
The WP requires a Quality Control Technician to perform an inspection to verify that the work was performed correctly.
Contrary to the above, on November 2, 1981, a Quality Control Technician had initialed and dated the verification for the correct installation af a pipe support shown in sketch 5(SK-5) which had not been installed as indicated.
This is a Severity Level IV Violation.
(Supplement I.D.3)
Pursuant to the provisions of 10 CFR Part 2.201, Public Service Company of Colorado is hereby required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full cortpliance will be achieved under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Consideration may be given to extending your response time for good cause shown.
Date December 22, 1981 6 w
'G. L. Madsen, Chief Reactor Projects Branch
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