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Notice of Violation from Insp on 900917-21 & 1001-05. Violations Noted:Failed to Include Detailed Procedures in Work Pack,Failed to Verify Insps,Failed to Segregate Noncoforming Fuses & Failed to Comply W/Fire Safety Program
	ML20058H655
Person / Time
Site:	Perry
Issue date:	11/14/1990
From:	Martin T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20058H653	List: IR 05000440/1990012; ML20058H651; ML20058H655;
References
	50-440-90-12, NUDOCS 9011210115
	Download: ML20058H655 (5)
	v • d • e

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NOTICE OF VIOLATION Cleveland Electric illuminating Company Docket No. 50 440 Perry Nuclear Power Plant License No. NPF-58 As a result of the inspection conducted on September 17 through 21, and October 1 through 5, 1990, and in accordance with 10 CFR Part 2, Appendix C -

General Statement of Policy and Procedure for NRC Enforcement Actions (1990),

the following violations were identified:

1. 10 CFR 50, Appendix B. Ci aerion V, as implemented by Section 5 of the Quality Assurance plan and Section 17.2.5 of the Updated Safety Analysis Report, require.; that activities affecting quality be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and that these activities be accomplished per these instructions, proceduses, or drawings.

Co' trary to the above:

a. On September 18, 1990 the air pack for MS!V IB21F022C was removed from the valve by a junior r.aintenance man utilizing a work package that did not contain detailed instructions appropriate to the circumstance for removal bt an individual with this skill level. As a result, hold dou sits on the Norgren valves were partially removed resulting in partial disassembly of the air pack. The "as found" condition of the air pack was lost even though the licensee had made previous commitments to maintain the "as found' condition so NRC inspectors could witness the testing and disassembly of the air pack (440/90012-OlA).

b. Section 6.4 of Perry Administrative Procedure PAP-1912, Revision 3, " Burn Permits for Ignition Sources," required that the responsible supervisor verify that all required inspections, signatures, notifications and compensating actions were complete prior to signing the burn permit. On October 2, 1990, the responsible supervisor signed a burn permit for burning, welding, and grinding on elevation 620 of the off-gas building prior to verification that all required inspections and signatures were complete (440/90012-01B).

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

2. 10 CFR 50, Appendix 3, Criterion XV, as implemented by Section 15.3.1 of the Quality Assunnce Plan and Section 17.2.15.2 e. of the Updated Safety Analysis Report, required that nonconforming material be segregated, where practical, to prevent inadvertent installation or use.

Contrary to the above, ten boxes of nonconforming fuses were located in the same storage drawer of a fuse cabinet in the main warehouse with several boxes of acceptable fuses of the same type (440/90012-02).

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

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1 Notice of Violation 2 1

3. Facility Operating License NPT-58, Section 2.C(6) required that the licensee comply with all provisions of the approved fire protection '

program as described in the Final Safety Analysis Report and a;;, roved in the Safety Evaluation Report dated May 1982 and Supplements Nos.1 i through 10 thereto, final Safety Analysis Report, Section E.2(c) stated that the fire pum.n conformed to National Fire Protection Association (NFPA) Standard Number 20. NFPA Standard Number 20 Section 11-3.1 required an annual test of the fire pump to determine the ability of the fire pump assembly (pump, driver and controller) to perform satisfactorily at peak loads. Section 11-3.3 required that any significant reduction in the operating characteristics of the fire pump assembly be reported to the owners and that repairs be made immediately.

Final Safety Analysis Report, Section E.2(e) indicated that the largest flow demand for a single pump was 3750 gallons per minute at 85 psi.

Contrary to the above:

a.. The electric driven fire pump and the diesel driven fire pump were not adequately tested in that the fire aumps were not tested at ,

shutoff pressure during tests on Septem)er 21987; March 12,1989; and September 9,1990(440/90012-03A).

b. Corrective actions were not initiated after the electric driven fire pump tests dated September 2, 1987; March 12, 1989; and September 9,1990; indicated significant pressure reduction {30%,

in the operating characteristics o. the 33% andassem)1y.

fire pump 35% res)ectively)ddition, In a the diesel driven fire pump test

, results dated September 2, 1987; March 12, 1989; and September 9, i 1990, did not record the engine speed or the pump speed at over capacity to determine the operating characteristics of the fire pump (440/90012 038),

c. The electric fire pump test results dated Sc)tember 2,1987, March 12, 1989, and September 9,1990, and tle diesel fire pump test results dated March 12, 1989, did not demonstrate that each fire pump could meet the demand of 3750 gallons per minute at 85

, psi (440/90012-03C). >

l This is a Severity level IV violation (Supplement ().

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110tice of Violation 3 Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) the corrective actions that have been taken and the results achieved; (2) the corrective actions that will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

NOV 141990

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CONTENTS ~

I Section Paae 1.0 Pri nci pal Persons Contacted. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Licensee Action on Previous Inspection items.............. 3 3.0 Introduction to the Evaluation and Assessment of Maintenance............................................. 3 3.1 Performance Data and System Sel ection. . . . . . . . . . . . . . . . . . . . . 4 3.1.1 Historic Data............................................. 4 3.1.2 System Selection.......................................... 5 3.2 Description of Maintenance Philosophy.... ................ 5 3.3 Observation of Current Plant Conditions & Sngoing Work.... 5 3.3.1 Current Material Condition................................ 5 3.3.2 Ongoing Work.............................................. 7 3.3.2.1 Ongoing Electrical Maintenance. . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.3.2.2 Ongoing Mechanical Maintenance............................ 8 3.3.2.3 Ongoing Instrument and Control Hairtenance............... 10 3.3.2.4 Main Steam Isolation Valve f ailure to Close. . . . . . . . . . . . . .11 3.3.2.4.1 Synopsis of Event........................................ 11 3.3.2.4.2 Ongoing MSIV Maintenance / Troubleshooting. . . . . . . . . . . . . . . . . 12 l 3.3.2.4.3 Past MSIV Maintenance History............................ 13 3.3.3 Rad i ol og i cal Control s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 3.3.4 Maintenance Facilities, Material Control, and Control of Tools and Measuring Equipment....................... 15 3.3.4.1 Maintenance Facilities................................... 15 3.3.4.2 Material Control......................................... 16 3.3.4.3 Control and Calibration of Measuring and Test Equipment.............................................. 17 3.4 Review and Evaluation of Maintenance Accomplished........18 3.4.1 Backlog Assessaant and Evaluation........................ 18 3.4.1.1 Corrective Maintenance Backlog. . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3.4.1.2 Preventive Maintenance Backlog. . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.4.2 Review and Evaluation of Completed Maintenance. . . . . . . . . . .19 3.4.2.1 Past Electrical Maintenance.............................. 19 3.4.2.2 Past Mechanical Maintenance. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.4.2.3 Past Instrumentation and Control Maintenance............. 23 3.5 Fire Protection.......................................... 26 3.5.1 Fire Protection Activities............................... 26 3.5.2 Ongoing Fire Protection Maintenance Activities........... 27 3.5.3 Past Fire Protection Maintenance fr.tivities.............. 27 3.6 Maintenance Work Control................................. 28 ,

3.7 Engineering and Technical Support. . . . . . . . . . . . . . . . . . . . . . . . 30 ,

3.7.1 System Engineering....................................... 30 '

3.7.2 Nuclear Engineering Department........................... 31 3.8 Review of Licensee's Assessment of Maintenance. . . . . . . . . . . 31 3.8.1 Audit and Surveillance Reports........................... 31 3.8.2 Maintenance Sel f- Assessment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 3.8.3 Qu al i ty Con trol Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 3.8.4 Trend i rig An alys i s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2 4.0 Synopsis................................................. 33 4.1 Overall Pl ant Performance. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 4.1.1 Historic Data............................................ 33 4.1.2 Pl a n t Wal kdown s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3 4.2 Management Support of Maintenance........................ 34 4.2.1 Management Commitment and Involvement.................... 34

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4.2.2 Management Organization and Admit -tration............... 34 i 4.2.3 Technical Support................... .................... 34 i 4.3 Implementation of Maintenance. . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 4.3.1 Work Control............................................. 35 4.3.2 Pl ant Maintenance Organization. . . . . . . . . . . . . . . . . . . . . . . . . . . 36

4.3.3 Maintenance Facilities, Equipment and Material Contro1................................................ 36 '

4.3.4 Personnel Control........................................ 36 5.0 Exit Meeting............................................. 37 !

Appendix A: Acronyms................................................. 38 l i

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