ML20237K522

Forwards List of Issues & Questions That Need to Be Addressed as Result of Findings During NRC Tour of Facility on 870707,for Review & Action If Necessary

ML20237K522
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	07/07/1987
From:	Raymond W NRC
To:	Pelletier J VERMONT YANKEE NUCLEAR POWER CORP.
Shared Package
ML20237K478	List: IR 05000271/1987012 ML20237K475 ML20237K496 ML20237K522
References
IR-87-12, NUDOCS 8708270202
Download: ML20237K522 (3)

Text

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ATTACHMENT I' t, IR ~B7-12 1 of 3 UNITED STATES NUCLEAR REGULATORY CONNISSION YERMONT YANKEE RESIDENT OfflCE Po box 176 VERNON, VERMONT 05354 MEMORANDUM July 7,1987 FOR: Jim Pelletier, Plant Meneger vfROM: Bill Raymond, SRI VY

SUBJECT:

Facility Tour Findings - July 7,1987 i The items on the attachment were noted during the facility tour on July 7, 1987 and are provided for your review and action as necessary. Please contact the onsite resident inspector when your steff is ready to discuss your evaluation of the items and the status of octions taken. Please note the items and the plant's response will be addressed in a routine I inspection report.

Thank you for your time and attention to these matters, and for your especially helpful assistence during the f acility tour.

k William J. Re and f cC.

8708270202 870821 l .

PDR ADOCK 05000271 Bill Russell O PDR Harold Eichenholz Geoff Grant'

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ISSUES AND nUE9TIONS THAT NEED TO BE ADDRESSED A9 A FEEULT OF FINDINGS FPOM A )

NRC TOUP OF THE FACILITY ON JULY 7. 1987 )

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1. Instrument Calibration Stickers. Calibration stickers on several instruments located in the c on trol room and the plant (for example, radiation ,

monitors en CRP 9-2, Rack 10 instruments, LI 19-16 Reactor Well Level, etc) {

indicated old cal ibr e t i on detes (dating back to 1983) and/or contained dual i stickers indicating two calibration dates. Have the instruments been )

cal i br & ted wi thi n the proper interval? If so, what is the function of the j stickers? Should they be updated or removed? l 1

2. Seismic Anchorage of Electrical Equipment (Switchgear, MCC's, etc.) {

Describe the actions taken in response to a 1983 NRC Generic Letter to address  !

the adequacy of electrical equipment mountings for seismic loads. What is the l status of any corrective actions identified from a review of the issue?  !

Sp e c i f i c al 1 y, wh+t additional actions should be taken to address: (i) open or partially secured cabinet doors; (ii) anchorage for the Switchgear S&9 )

transformers - the transformer for SWGR 9 was held down by 3 of 4 bol ts ; and )

(iii) rigidity verification of cc-trol room panels.

3. Tracking Deficiencies in the Work Control (MR) Process. How do the ]

present administrative controls for the MR process track discrepancies so'that J personnel in the field know that identified deficiencies have been entered j

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into the system? Should administrative con tr ol s be upgraded to provide l oc al identification (at the component) that discrepant conditions have been noted .

and entered into the system? -

4. Personnel Badging & Dosimetry. Describe the circumstances related to the discovery of a worker's security ID badge and dosimetry on the Reactor j Bu i l di ng (RB) 280 ft elevation. What further corrective action are needed, if i any?

5. Control of Explosive Stud Drivers. Describe the circumstances related to the discovery of an unattended explosive stud driver on the Reector Building 280 ft elevation. What are the in tended secur i ty measures f or such equipment.

Whet further corrective &ctions are necessary, if any?

6. Housekeeping Items. It was noted that the overall pl an t cleanliness and equipment material conditions was excellent, which is indicative of a good housekeep i ng pr ogr am and maintenance program. The effectiveness of the FM p r ogr ern for valve maintenance was notable based on the observation of few pecking leaks.

However, the f ol l owi ng ...j n or housekeeping and material condi t i ons war ran t f ol l owup and/or verification that the discrepancies have been entered in the work c on t r ol system:

o Email emounts of trash and dirt in ena around 24 VDC ECCS battery enclosures. In particular, the residue from previ ous el ec trol yte spills shculd be remtved to assure p o t e n t i al bettery leakage is readily identified, o Disposal of vacuum cleaner filter cartridges in the spent fuel pool .

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o Clutter in the cuerhead above the reactor' water cleanup pumps; damaged l aggi ng on a3 inch pipe that runs above 1 the dividing wall between the RCU pump cubicles. l o P1astic covering the sp1 ash guard beneeth the -he ater/ cool er-  !

unit in the 'A' diesel room l l

o Valve RHR V10-65A stem packing leak -

o smal l leek into the 'B' RHR pump casing drain from the seal cooler 1ine o Small amount of lube oil on the 'A' diesel skid from a flange leak beneath the wooderd governor; oil in catch pens beneeth injectors o Full core display for CR 10-27 on CRF 9 loss of beck .l i t indication for full out position o Operating indication (bulb out) for SEF-3 in the Cable Vault 4

o Conduit couplings not fully tightened for CAD cables in conduits CR-02229-SE, 228, 227, 220 - (back of cable vault) o 3 Missing screws. in Junction box cover beneath East cable )

vault control & indication penetration j i

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