ML18064A396
| ML18064A396 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/29/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18064A395 | List: |
| References | |
| 50-255-94-14, NUDOCS 9410070046 | |
| Download: ML18064A396 (2) | |
Text
NOTICE OF VIOLATION Consumers Power Company Palisades Nuclear Generating Plant Docket No.
50-255 License No. DPR-20 During an NRC inspection conducted on August 11 through September 27, 1994, violations of NRC requirements was identified.
In accordance with the MGeneral Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:
- 1.
Palisades Technical Specification 4.0.5.a states inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as ~equired by 10 CFR 50, Section 50.55a(f),
except where specific written relief has been granted by the NRC.
ASME Ccide,Section XI, IWV-3522, "Exercising Procedure," states "Check valves should be exercised to the position required to fulfil.l their function.... " The IST program identified the boric *acid injection to chargin*g pump suction check valves (CK-CVC2138 and CK-CVC2139) as having an.open ~afety function.
Contrary to the above, from March 1991 to May 1994, for check valves CK-CVC2138 and CK~CVC2139, test procedure Q0~18, "Concentrated Boric Acid Pumps," did not exercise the valves to the full flow open position as stated in the IST program.
This is a Severity Level IV.viol~tion (Supplement 1:0.3). (50-255/94014-
- 29)
- 2.
10 CFR 50.59, "C~anges, Tests and Experiments," states that a licensee may make changes in the facility without prior Commission approval, unless the proposed change involves an unreviewed safety question..
10 CFR 50.59 further states that a proposed change shall be deemed to involve an unreviewed safety question if the probability of occurrence or the consequences of an accident or malf~nction of equipment important to Safety previously eval.uated in the safety analysis report may be increased.
Contrary to the above, from October 3, 1992, to March 18, 1994, the condensate storage tank (CST) temperature was allowed to exceed the design basis temperature of 120 degrees F. without fully evaluating the effects on plant operation or the de$ign.
The increase in CST temperatur~ had a nonconservative impact on several accident analyses in Chapter 14 of the FSAR that were not evaluated for a possible unreviewed safety question.
This is a Severity Level IV violation (Supplement I.D.3)..
(50-255/94014-54) 9410070046 940929 PDR ADOCK 05000255 G
- 2.
The inspection showed that steps had been taken to correct the identified violations and to prevent recurrence. Consequently, no reply to the violations is required and we have no further questions regarding this matter.
Dated at Lisle, Illinois, this 1..91.b_ day of September 1994