ML20009G878
| ML20009G878 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/15/1981 |
| From: | Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20009G876 | List: |
| References | |
| 50-266-81-11, 50-301-81-13, NUDOCS 8108050173 | |
| Download: ML20009G878 (2) | |
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Appendix A i,
J Wisconsin Electric Power Docket No. 50-266 Company Docket No. 50-301 l
As a result of the inspection conducted on June 1-30, 1981, and in accord-ance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the following violations were identified:
l 1.
Technical Specification 15.3.B.2.C states in part, "Any valve required for the functioning of the system during accident conditions may be inoperable provided repairs are completed within 24' hours.
j Contrary to the above, on June 21, 1981, valve 1-831A was found locked shut. This manual, normally locked open, valve is the discharge outlet i
isolation *.o the Unit I sodium hydroxide addition tank.
Investigations revealed that the valve was locked shut on June 17, 1981, therefore the velve was inoperable for a period in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j This is a Severity Level IV violation (Supplement I).
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2.
Technical Specification 15.3.14.E states, "All penetration fire barriers protecting: safety related areas shall be functional." Technical Speci-
-fication 15.3.14.E.1 states, "In the event of a penetration fire barrier impairment a continuous fire watch shall be established on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."
Contrary to the above, on June 23, 1981, the inspector noted the west fire barrier door between the 3D and 4D diesel rooms propped open with-no persodnel present in either diesel room.
i This is a Severity Level IV violation (Supplement I).
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3.
10 CFR 50 Appendix B Section XVII requires in part that, " Inspection and test records shall, as a minimum, identify the inspector or data recorder,' the type of observation, the results, the-acceptability, and the action taken in connection with any deficiencies noted." This re-quirecent is implemented, in part, in the Operating Point Beach Nuclear Plant Administrative Control Policies and Procedures Manual Section 4.16 which states in part, "All out of service readings shall be identified on the log sheet and an entry made in the remarks section explaining the condition and actions taken."
-Contrary to the above, numerous out-of-specification readings in the j
auxiliary building and turbine building operating logs' for May,1981 l
are neither properly-identified nor explained. More specifically, on the auxiliary building logs 10 of 136 out-ofspecification conditions l-l l
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' 8108050173 810715 PDR ADOCK 05000266
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Appendix A were not properly identified.
On the Unit I turbine building logs 9 of 85 out-of-specification conditions were not properly identified, and on the Unit 2 turbine building logs 15 of 91 out-of-specification conditions were not properly identified. Among those missed were com-ponent cooling water flow to the excess letdown heat exchanger, battery charger voltage, and condensate storage tank levels. Additionally, for those readings properly identified as out-of-specification, the explana-tion and actions taken remarks, in most cases, were inadequate.
This is a Severity Level V violation (Supplement II).
4.
Technical Specification 15.6.8.3.A requires in part that, "For temporary changes to major procedures un'ar the jurisdiction of Maintenance, In-strumentation and Control, Reactor Engineering, or Chemistry and Health Physics which do not change the intent, changes may be made upon approval of the cognizant group head and a Duty and Call Superintendent."
Contrary to the above, the following procedures which received group head approval as temporary changes during their performance were not approved by a Duty and Call Superintendent until after their perfor-mance; ICP 4.25 Intermediate Range Calibration; ICP 4.26 Power Range Calibration; ICP 4.30 Refueling Source Range Drop-In Detector Cali-bration.
This is a Severity Level V violation (Supplement II).
The inspection showed that action had been taken to correct the identified items of noncompliance and to prevent recurrence. Consequently, no reply to these items of noncompliance is required and we have no further questions regarding this matter.
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Dated R. F. Heishman, Acting Director Division of Resident and Project Inspection