ML20215D927
| ML20215D927 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/19/1986 |
| From: | Larson C NORTHERN STATES POWER CO. |
| To: | Guldemond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8610140362 | |
| Download: ML20215D927 (3) | |
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Northem States Power Company 414 Nicollet Mall Minneepoks. Minnesota 55401 Telephone (612) 330 5500 August 19, 1986 Mr W G Guldemond, Chief Projects Branch 2 U S Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to Inspection Reports No. 282/86007 and 306/86007 In response to your letter of July 23, 1986, which transmitted Inspection Reports No. 282/86007 and 306/86007, the following information is offered.
Violation #1 10 CFR 50, Appendix B, Criterion II, states, in part, that the quality assurance program shall provide control over activities affecting the quality of identified structures, systems, and components, to an extent consistent with their importance to safety, and that activities affecting quality shall be accomplished under suitably controlled conditions.
Northern States Power Operational Qualify Assurance Plan, Section 16.2, Maintenance Control, states, in part, that measures shall be established for the control of maintenance repair and modification activities are performed in a manner consistent with its importance to safety and that upon completion of repairs and modifications the affected systems and components are inspected and tested to determine that the required work was performed satisfactorily.
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Contrary to the above, the following examples of failure to adequately control modification activities were identified:
a.
On May 29, 1986, and again on June 10, 1986, with Unit 1 at full power, work adversely affecting plant operation (disabling of a rod position step counter) was performed with inadequate controls.
b.
From the time of Unit I startup on April 10, 1986 until May 4, 1986, MV-32023, which has plant safety functions, was left without its limit switch cover in place following modification activities.
l 8610140362 860319 DR ADOCK 05000282 AUG 2 71986 hgo PDR 35 el
r-4 MR W G Guldemond, Chief August 19, 1986 Page 2 Northem States Power Company This is a Severity Level IV Violation (Supplement I).
NSP Response A Stop Work Order was issued and additional controls were instituted over construction work on site. Improvements in the control of modification activities have been the subject of increased management concern for the past several months.
Some improvements have been implemented, as outlined in our July 30, 1986 response to Inspection reports No. 282/85021 and 306/85019. A task force has been formed to study the need for additional administrative improvements in control of modification activities. We will continue to keep the Resident Inspectors and your office informed of these activities.
Violation No. 2 10 CFR 50, Appendix B Criterion XVII, Quality Assurance Records, states, in part, that suf ficient records shall be maintained to furnish evidence of activities affecting quality and that the records shall include at least the Operating Logs. Northern States Power Operational Quality Assurance Plan, Section 19.1, implements this requirement.
Contrary to the above, as of 7:00 am on May 2, 1986 neither the Reactor Log nor the Operations Log contained entries related to the missing valve cover on MV-32023 which had been noted on May 1.
(See Violation 1 above.)
This is a Severity Level IV Violation (Supplement I).
NSP Response Personnel involved in the event discussed reporting and logging require-ments at the time of the event and concluded, under existing instructions, that the specified log entries were not required and that the event was not reportable to the NRC. Administrative instructions concerning logging will be expanded and clarified by November,1986, at which time full compliance will be achieved.
Violation No. 3 Technical Specification 6.5 states, in part, " detailed written procedures
. covering areas listed below shall be prepared and followed... C.
maintenance and test Contrary to the above, on March 24, 1986, during testing of substation equipment, a relay technician failed to properly follow written procedures which resulted in loss of one source of offsite power and automatic starting of both emergency diesel generators.
This is a Severity Level IV Violation (Supplement I).
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MR W G Guld mond, Chief August 19, 1986 Page 3 Northom States Power Company NSP Response This event has been discussed with all relay technicians working on equipment at Prairie Island in accordance with standard policy of the Maintenance and Testing Department. Adherence to written procedures has been re-emphasized. -Full compliance has been achieved.
In addition, a task analysis of the relay panels in the substation will be performed to identify potential rearrangement of equipment and re-labeling to help avert future human errors.
C E Larso VicePresidendNuclearGeneration CEL/EFE/ dab c: Regional Administrator - III, NRC Resident Inspector, NRC G Charnoff