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Sb RECORD OF ALLEGATION PANEL DECISIONS SITE:
Milh PANEL ATTENDEES:
we ALLEGATION NO.:
@l-91-4-ooSfi Chairman - 3. T D% q m 5 DATE:
g m GYO (Mtg.@2345)
Branch Chief - P. C. U>cmg er PRIORITY:
High @
Low Section Chief ( AOC) - f. Af. //ek SAFETY SIGNIFICANCE: Yes No Unknown Others-2b.#Ndt R.l. hwib CCNCURRENCE TO CLOSE0VT: DD h SC
- 2. C. 9ed CONFIDENTIALITY GRANTED: Yes
- k. Ct. Na (SeeAllegationReceiptReport)h IS THEIR A DOL FINDING:
Yes No IS CHILLING EFFECT LETTER WARRANTED:
Yes No i
HAS CHILLING EFFECT LETTER BEEN SENT:
Yes No HAS LICENSEE RESPONDED TO CHILLING EFFECT LETTER:
Yes No ACTION:
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5 Allegation File,(ef) RI-91-A-0082,0084,0085,0096,0099,0H6 T. Shedlosky, SRI, Millstone J. Stewart E. Kelly w. R p.. A
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UNITED ST ATES
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'k NUCLEAP *tEGULATORY COMMISSION I
REGION I f*- ~'i I
475 ALLENDALE ROAD
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KING OF PRUSSIA. PENNSYLVANIA 19406 K.(I W Docket Nos. 50-336 File Number RI-91-A-0082 Northeast Nuclear Energy Company ATTN:
Mr. E. J. Mroczka Senior Vice President - Nuclear Engineering and Operations Group P.O. Box 270 Hartford, Connecticut 06141-0270 Dear Mr. Mroczka.
The U.S. Nuclear Regulatory Commission recently received information concerning activities at the Millstone Nuclear Power Facility, Unit 2. The details are enclosed for your review and follow-up.
We request that the results of your review and disposition of these matters be submitted to Region I within 30 days of the date of receipt of this letter. We request that your response contain no personal privacy, proprietary, or safeguards information so it can be released to the public and placed in the NRC Public Document Room. If necessary, such information shall be contained in a separate attachment which will be withheld from public disclosure.
The affidavit required by 10 CFR 2.790(b) must accompany your response if proprietary information is included. Please refer to 61e number RI-91-A-0082 when providing your response.
The enclosure to this letter should be controlled and distribution limited to personnel with a "need to know" until your investigation of the concern has been completed and reviewed by NRC Region I. The enclosure to this letter is considered Exempt from Public Disclosure in accordance with Title 10, Code of Federal Regulations, Part 2.790(a). However, a copy of this letter excluding the enclosure will be placed in the NRC Public Document room.
The response requested by this letter and the accompanying enclosure are not subject to the clearance procedures of the Of6ce of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation with us is appreciated. We will gladly discuss any questions you have concerning this information.
Sinc ely, l
C. les W. Eehl, DPrector Division of Reactor Projects
Enclosure:
(10 CFR 2.790(a) Information)
W3 L h-
a ENCLOSURE LIMITED DISTRIBUTIONsNOT FOR PUB.LIC DISCLOSURE.%.
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v Issue 1:
ne wiring diagrams insvising Reactor Coolant Pump RID circuits have not been updatedfollowing modifications made under a PDCR to replace RTD circuit kmfe suitches uith Weidmuller Test Blocks. Drawing No. 25203-31069, Sheet 5, liev. 3, dated August 29,1989, does not reflect the changefor at least 4 RTD circuits (TCD, TCC, TCA, TCB). De instrument loop diagrams (Drawing No. 25203-28500, Sheets 140 & 146) show the Weidmuller Test Blocks. Also, in Drawing number 25203-31069, Sheet 5, thejumpers shown betueen cable lead 1 and the cable shield ground on the loop diagrams are not shown. In addition, access to the GRITS system, to wnfy the latest drawing resisions, is restricted in that personal access codes are only validfor 30 days.
Request 1:
Please discuss the validity of the above assertions. If discrepancies are found, please assess the significance of the discrepancies with respect to plant operation and safety and discuss any actions taken or planned to correct these discrepancies.
Issue 2:
The Steam Generator No. 2 mid-loop instrumentation (L-122) was not " operable" during drain-dounfor tube inspections on May 2,1991. GEM switches werefound to be
- fro:.en" on in place. In addition, L-112 had an electronic noise problem caused by an improperly installedjumper. Thus licensee commitment that tuo monitors be operable during drain down condition was not being met.
Request 2:
Please discuss the validity of the above assertions. If any discrepant conditions are identified, please discuss their significance with respect to plant operation and safety during the Steam Generator No. 2 drain-down evolution. Also please discuss any actions taken or planned to correct these deficiencies.
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Issue 3:
Pressure indicating instrument (Pl 6350 A/B and P16351 A/B) and mountingsfor 8
I service water fSW) supply to emergency diesel generators (EDG) are not seismically mounted. Any kind ofshock uvuld be suficient to knock the gauge arul valve ofof the strainer. Additionally, the location of the taps as shown on the P&lD apparently does not coincide with the actual tap locations.
Request 3:
Please discuss the validity of the above assertions. If the assenions are valid, please
.i discuss their effect on the safe operation of SW supply to the EDG. Please provide any actions taken or planned to ensure that seismic requirements for these instruments-are being met.
Issue 4:
L On May 3,1991, the Unit 2 Stack Radiation Monitor (RM 8132) was inoperable as a result of beingflooded uish water. This monitor uvuld have been inoperable anyway, as airflow had been isolated. Filling and pressure testing of Steam Generator (SG)
- 1 was undency during the same time period. Problems with valve line-upsfor the rad monitor and the SG testing contributed to theflooding and monitor inoperability.
l Additionally, health physics (HP) controls during removal of the unterfrom the j
monitor was inadequate resulting in contamination ofpersonnel.
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Request 4:
L Please discuss the validity of the above assertions. If discrepancies are confirmed, i
i please discuss actions that you have taken or will take to ensure that plant procedures i
regarding rad monitor operation, conduct of tests, and HP activities are being used properly.
Issue 5:
Procedure discrepancies czist between OP-2336E and SP-2617A for the restoration of
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the line-up of the radiation monitor (RE-245), and its associated sample pump.
l Operators routinelyfail to perfonn OP-2336E, Section 5.1, Step 5.L13 which is to immediately close AOV-244A/B and AOV-245 when securingfrom condensate
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polishingfacility discharges. Thisfailure tofollowprocedures results in the sample pump to radiation monitor (RM-245) continuing to operate when the tank discharge is secured.
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LIMITED DISTRIBUTION?NOT-FOTOPUBLICQlSCLOSURE_.
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(j Request 5:
Please discuss the validity of the above assertions. If any discrepancies are identified concerning procedure noncompliance, please discuss their significance on the operation of adiation monitor RM-245. Please discuss any corrective actions taken or planned, to ensure operators are meeting procedural and technical specification requirements.
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Issue 6:
i Thefollowing discrepancies have been idennfied during an evaluation of Work Order AWO-Af2-91-M411. These discrepancies idennfy continued non-compliance with procedures and poor respon.se of operations and management to recurring problems with radiation monitor RE-245.
The sample pump continues to run when the tank discharge stops at 15% tank l
a.
level (TK-11).
b.
The " Low Flow ~ swuch does not always see a lowpow condition when TK-10 i
and TK-11 discharge pumps stop. The head of water in the pipe and tidal conditions afect thepow of unter.
Operations normally rely on the 15% tank levelpump trip to stoppow causing
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a lowpow to trip shut RE-245 discharge valve, and AOY245. IfAOY244A/B are shut and no lowpow condition exists, RE-245 sample pump will continue j
to run until AOY245 is shut.
d.
Changes to OP-2336E were identified in 1989 to prevent the problems l
idennped by AWO-M2-91-W411. However continued idennfied procedure non-compliance by operations has caused repeated problems.
I Request 6:
Please provide an assessment of the above discrepant conditions. If the assertions are valid, please discuss their safety significance and effect on operation of radiation monitor RE-245. Please discuss any corrective actions that are being used to correct
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the problems.
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r LIMITED DISTRIBU{ ION-MOR PUBLTbOISCLOS{TRU' v
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S5 RECORD OF ALLEGATION PANEL DECISIONS f
SITE:
Ali N5 km E PANEL ATTENDEES:
ALLEGATION NO.:
21 4 - oo 8 (o Chairman -
I 7.
tun gq DATE: 8A4Y91 (Mtg. I 2 3 4 5)
Branch Chief -
PRICRITY:
High 5e M Low Section Chief ( AOC) - E.41, ke[
SAFETY SIGNIFICANCE: Yes No Unknown Others
~J. 9. Dur v-DD h SC
- 1. S. $ 4ead CONCURRENCE TO CLCSEOUT:
(SeeAllegationReceiptReport)h CONFIDENTIALITY GRANTED: Yes 2[. hmec3h 1
IS THEIR A DDL FINDING:
Yes No IS CHILLING EFFECT LETTER WARRANTED:
Yes No HAS CHILLING EFFECT LETTER BEEN SENT:
Yes No HAS LICENSEE RESPONDED TO CHILLING EFFECT LETTER:
Yes No ACTION:
I) bew) 2%DRc_,aCA
[D i25 > iD rQhr lo9 r B.O 1 ud IAk & ar t.k~,dem 2) i a) 9 5) i NOTES:
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