ML17305A850

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Notice of Violation from Insp on 900304-0414.Violations Noted:Four Channels of ex-core Neutron Flux Logarithmic Power Level Instrumentation Deenergized & Rept 90-RC-0009 Did Not Include Quantitative Acceptance Criteria
ML17305A850
Person / Time
Site: Palo Verde  
Issue date: 05/21/1990
From: Richards S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17305A848 List:
References
50-528-90-12, 50-530-90-12, NUDOCS 9006050130
Download: ML17305A850 (4)


Text

APPENDIX A NOTICE OF VIOLATION Arizona Public Service Company Palo Verde Units 1 and 3

Docket Numbers 50-528 and 50-530 License Numbers NPF-41 and NFP-74 During an NRC inspection conducted on March 4 through April 14, 1990, three violations of NRC requirements were identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1990), the violations are listed below:

A.

Unit 1 Technical Specifications, Section 3.3. 1, requires in part that a minjmum of two channels of Excore Neutron Flux Logarithmic Power Level - High instrumentation will be operable in Mode 5, and allows for operation with only one channel provided certain Action Statement requirements are met.

Contrary to the above, from March 21, 1990, until March 24, 1990, all four channels of Excore Neutron Flux Logarithmic Power Level instrumentation were deenergized by licensee personnel to perform cabinet and drawer repairs while Unit 1 was in Mode 5.

This is a Severity Level IV Violation applicable to Unit 1 (Supplement I).

B.

10 CFR Part 50, Appendix B, Criterion V, states in part that instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

Contrary to the above, Material Non-Compliance

Report, 90-RC-0009, Conditional Request
Release, did not include an appropriate quantitative acceptance criteria in that it did not specify the maximum allowable torque authorized for use on valve 3PRC-B-V-207

'he conditional release appeared to allow a maximum torque of 75 ft-lbs, whereas the proper maximum allowable torque was 30 ft-lbs.

This is a Severity Level IV Violation applicable to Unit 3 (Supplement I).

C.

Unit 3 Technical Specifications, Section 6.8. 1, states in part:...

"Written Procedures shall be established, implemented, and maintained covering the activities referenced below:

f.

Fire Protection Program implementation."

This program is implemented, in part, by licensee Procedure 14AC-OFP03, "Control of Combustible/Flammable Materials and Liquids" which states in part in paragraph 3.2. 10, that "combustible material shall not be stored next to outdoor safety-related water storage tanks,"

9PPg/50 i30 90052 >.

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Contrary to the above, on March 5, 1990, two apparently untreated

. wood packing crates, an apparently full 55 gallon drum with a National Fire Protection Association tag labeled 3 for flammability (extreme hazard) and a number of other 55 gallon drums similarly marked were stacked immediately adjacent to the Unit 3 Condensate Storage Tank (a safety-related tank required for safe shutdown).

This is a Severity Level IV Violation applicable to Unit 3 (Supplement I).

Pursuant to the. provisions of 10 CFR Part 2.201, Arizona Public Service Company is hereby required to submit a written statement or explanation to the U.

S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Mashington, DC 20555, with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspection office at the Palo Verde Nuclear Generating Station, within 30 days of the date of the letter transmitting this Notice of Violation (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 an adequate reply is-not received within the time specified in this Notice,'n 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 your response time for good cause shown.

FOR THE NUCLEAR REGULATORY COMMISSION

>c ar s,

)e Reactor Projects Branch Dated at Malnut Creek, California this 3l-day of wAY 1990

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