ML20210R658

Notice of Violation from Insp on 970508-0630.Violation Noted:On 970624,licensee Identified That B RHRSW Cooling Tower Fan Rendered Inoperable for Planned Maintenance W/O Demonstrating Operability of Remaining AC Sources

ML20210R658
Person / Time
Site:	Fermi
Issue date:	08/26/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210R640	List: IR 05000341/1997007 ML20210R635 ML20210R658
References
50-341-97-07, 50-341-97-7, NUDOCS 9709030208
Download: ML20210R658 (3)

Text

l NOTICE OF VIOLATION Detroit Edison Company Docket No. 050 341 Fermi 2 License No. NPF-43 j

During an NRC inspection conducted from May 8 through June 30,1997, violations of {

NRC requirements were identified, la accordance with the " General Statement of Policy )

4 and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed j below.

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1. Technical Specification (TS) 3.7.1.5 requires that the Ultimate Heat Sink, comprised of two one half capacity residual heat removal (RHR) reservolts, be operable.

Technical Specification 3.7.1.5 further requires that at least one cooling tower with two cooling fans be operable for each RHR reservoir. In addition, TS 3.7.1.5 requires that with cne or more of the requirements of TS 3.7.1.5. not satisfied, the affected reservoir (s) be declared inoperable and the action required by TS 5.7.1.5 d or e be taken.

Technical Specification 3.7.1.5.d requires that with one reservoir inoperable, the associated residual heat removal service water (RHRSW) subsystem, emergency equipment service water subsystem, and diesel generator cooling water subsystem be declared inoperable and the action required by TSs 3.7.1.1, 3.7.1.3, and 3.7.1.4. be taken.

TS 3.7.1.4 requires that with one or more diesel generator cooling water subsystem inoperable, the associated diesel generator be declared inoperable and the action required by TS 3.8.1.1 or 3.8.1.2, as applicable, be taken.

TS 3.8.1.1, requires that with one or both diesel generators in une of the required onsite alternating current (AC) electrical powe' divisions inoperable, the operability of the remaining AC sources be demonstratso t,y performing Surveillance Requirement (SR) 4.8.1.1.1 within one hour and at least once per eight hours thereafter.

SR 4.8.1.1.1 requires that each of the required independent circuits between the offsite transmission network and the onsite Class 1E distribution system be determined operable by verifying correct breaker alignments and indicated power availability.

Contrary to the above, on June 24,1997, the licensee identified that the "B" RHRSW cooling tower fan was rendered inoperable for planned maintenance without demonstrating the operability of the remaining AC sources within the required one hour.

This is a Severity Level IV violation (Supplement 1).

2. Technical Specification SR 4.4.1.1.2 requires that each mechanical and electrical stop on the reactor recirculation pump motor generator set scoop tube be ,

demonstrated operable with overspeed setpoints less than 110 percent and 107 percent, respectively, of rated core flow, at least once per 18 months.

9709030200 970826 PDR ADOCK 05000341 0 PDR

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Notica of Violation 2-  !

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Contrary to the above, or$ May 24,1997, the inspectors identified that the reactor '

recirculation pump motor generator set scoop tube mechanical and electrical stops  ;

were not demonstrated operable with the required setpoints within an 18 month parlod. The SR was last successfully performed on July 6,1995.

This is a Severity Level IV violation (Supplement 1).

3. Technical Specification 6.8.1.s requires that written procedures be established, Irnplemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Appendix A of Regulatory Guide 1.33, Revision 2, Section 9.a, requires that maintenance that can affect the performance of safety related equipment be properly preplanned in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.

Administrative Procedure MMA11, Post Maintenance Testing," Revision 2, step 4.1.1.6 requires that the post maintenance testing (PMT) for a planned work activity be determined by reviewing t's PMT requirements contained in enclosures A through E to procedure MMA11. Enclosure D to MMA11, " Miscellaneous Equipment Testing," Step 1.3, states "If battery cells are added or replaced or battery capacity is potentially affected, perform a battery performance (disciwrge) test and/or service (load profile) test."

Contrary to the above, on April 15,1996, the inspectors identified that Cells 16, 17 and 18 of the Division 124/48 Volt Battery were replaced, which potentially affected battery capacity, without the licensee performing a battery performance test or a service test.

This is a Severity Level IV Violation (Supplement 1).

4. 10 CFR 50, Appendix B, Criterion XVI, " Corrective Action," requires that measures be established to assure that conditions adverse to quality, such as failures, rnalfunctions, deficiencies, deviations, or defective material are promptly identified and corrected, in the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.

Contrary to the above, on January 17,1997, the inspectors identified that a significant condition adverse to quality was not corrected to preclude repetition.

The cabinet alarm set point was not adjusted to provide adequate warning to prevent freezing of the instrument sensing lines for the Condensate Storage Tank

4 4 Notice of Violation 3-(CST) level transmitters. This resultod in a loss of the automatic swapover featuro to the supprossion pool for both the Reactor Coro isolation Cooling Systern and High Pressuto Coolant injection System, as well as CST levelindication and alarms in the control room. A similar event occurred in January 1992.

This is a Severity Lovel IV Violation (Supplomont 1)

Pursuant to the provisions of 10 CFR 2.201, the Detroit Edison Company is hereby required to submit a written statomont or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region lil, and a copy to the NRC Resident inspector at the facility that is subject of this Notico, within 30 days of the date of the lottor transmitting this Notice of Violation (Notico). This reply should be clearly marked as a " Reply to a Notico of Violation" and should include for each violation: (1) the reason for tho violation, or, if contested, the basis for disputing the violation, (2) the correctivo steps taken and the results achloved, (3) the corrective stops that will be taken to avoid further violations, and (4) the date when full compliance will be achloved. Your responso may reference or include previous docketed correspondence,if the correspondence adequately addressos the required response. If an adoquate reply is not recolved within the time specified in this Notice, an order or a Demand for Information may be issued as to why the licenso should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

' Because your response will be placed in the NRC PDR, to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can bo placed in the PDR without redaction, if personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such inform 0 tion. if you request withholding of such material, you Inug specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g. explain why the disclosure of information will create an unwarranted invasion of personal privacy or provido the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptablo response, please provide the level of protection described in 10 CFR 73.21, Dated at Lisle, Illinois, this 26th day of August 1997

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