ML17286B024
| ML17286B024 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/16/1991 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286B023 | List: |
| References | |
| 50-397-91-16, NUDOCS 9108300002 | |
| Download: ML17286B024 (5) | |
Text
APPENDIX A NOTICE OF VIOLATION Washington Public Power Supply System Washington Nuclear Plant No.
2 Docket No. 50-397 License No.
NPF-21 During an NRC inspection conducted from May 20, 1991 through June 21, 1991, a
violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991), the violation is listed below:
10 CFR 50, Appendix B, Criterion Y, "Instructions, Procedures and Drawings",
- states, in part, "Activities affecting quality... shall be.accomplished in accordance with these instructions, procedures or drawings..."
Administrative Procedure 1.3. 12 Revision 14, "Plant Problems - Problem Evaluation Request",
Paragi aph i.3. 12. 7.A, states, in part, "Any Supply System employee who observes a plant problem or a potential siqnificant problem should immediately notify his/her Supervisor and initiate a PER..."
Paragraph 1.3.12.3.A.1.5 defines a Plant Problem as, "A potential significant problem requiring disposition, corrective'ction or a reportability assessment."
Contrary to the above, a Problem Evaluation Request (PER) was not written when instances of degraded spring packs in Limitorque actuators were observed by Supply System emp)oyees dunng the testing and refurbishment of the following safety related motor operated valves:
FPC-MO-175 on 3/12/91 under MWR No.
AR3151 FPC-MO-172 on 3/19/91 under MWR No.
AR3149 These deficiencies were significant conditions potentially affecting the operability of the valves.
This is a Severity Level IV Violation (Supplement 1).
9208300002 92082h PDR ADQCK 05000397 Q
e l
l'l~,
Pursuant to the provisions of 10 CFR 2.201',
Washington Public Power Supply System is hereby required to submit a written statement of explanation to the U.
S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.
C.
20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Senior Resident Inspector, Washington Nuclear Project Unit 2, 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 further violations, and (4) the date when full compliance will be achieved. If 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.
Dated at Walnut Creek, California this ~<
day of August, 1991.
APPENDIX B NOTICE OF DEVIATION Washington Public Power Supply System Washington Nuclear Plant No.
2 Docket No. 50-397 License No.
NPF-21 During an NRC inspection conducted from May 20, 1991 through June 21, 1991, deviations from your written commitments were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions",
10 CFR Part 2, Appendix C, (1991), the deviations are listed below:
A.
In response to NRC Generic Letter 89-10, "Safety Related Motor-Operated Valve Testing and Surveillance,"
dated June 28, 1989, Washington Public Power Supply System, the licensee, stated that:
(1)
By June 28, 1990, the program description and schedule as required by the Generic Letter would be available for onsite NRC review (Supplement 2 to the Generic Letter extended that time to January 1,
1991. ), and (2)
The recommendations of the Generic Letter would be completed subject to certain schedule adjustments involving motor-operated valve (MOV) testing.
Contrary to the above, as of June 7, 1991, the following recommended actions had neither been addressed nor included in the licensee's established program:
l.
Emergency operating procedures had not been reviewed for the purpose of establishing the scope of the subject program as recommended in NRC response to question 6 of Supplement 1 to the Generic Letter.
2.
Nominal operatinq pressures were used in the program as the design basis for operab)lity of certain valves in lines connected to the reactor vessel, rather than the maximum differential pressure as described in recommended action "a" of the Generic Letter.
3.
Valve mispositioning had not been considered in determininq bounding differential pressure and flow conditions, as recommended sn NRC response to question 15 of Supplement 1 to the Generic Letter.
4.
Calculations for MOV sizing and switch settings had not considered the effects of high ambient temperature and seismic loading, as recommended in NRC response to question 16 of Supplement 1 to the Generic Letter.
5.
Thermal overload switch setting affect on the capability of MOYs to perform their designated safety function had not been addressed, as recommended in NRC response to question 21 of Supplement 1 to the Generic Letter.
910B300004 910B16 PDR ADOCK 05000397 8
B.
Page 8.3-30 of the MNP-2 FSAR includes a section on "Minimum Voltage",
which states in part:
"All Class lE motors; as a minimum, have torque characteristics suitable for the driven load to accelerate their connected loads to rated speed with only SOX of rated voltage applied to the motor terminals."
Contrary to the above, on June 6, 1991, the calculation for motor operated valve RCIC V-8 indicated that the Class lE motor was inadequately sized for SOX of rated voltage.
A voltage of 87K of rated voltage was used in the calculation determining motor suitability instead of SOX of rated voltage, as committed in the FSAR.
Please provide to the U.
S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Mashington, D.
C.
20555, with a copy to the Regional Administrator, Region V, and if applicable, a copy to the NRC Resident Inspector, in writing within 30 days of the date of this Notice, the reason(s) for the deviation, the corrective steps which have been taken and the results
- achieved, the corrective steps which will be taken to avoid further deviations, and the date when your corrective action will be completed.
Mhere good cause is shown, consideration will be given to extending the response time.
Dated g Walnut Creek, California this l~
day of August, 1991