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i MAY 2 1931.
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M This letter refers concerns that you provided to the NRC Regil, May 14,1991. The issues were related to:
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Wiring Diagram for Reactor Cooling Pump RTDs;
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Operability of Steam Generator Mid-Loop Instrumentation;
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Emergency Diesel Generators; Seismic Qualification of
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Inoperability of Stack Radiation Monitor Due to Flooding and Is
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'I Failure to Isolation the Condensate Polishing Facility Waste Neu
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Sump Per Procedure; and, Restoration of Radiation Monitor and the Associated Sample Pu
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Waste Neutralization Sump.
Attached are the issues as we intend to characterize them to the li:
any further questions, or ifI can be of further assistance in this mat
.j at (215) 337-5225.
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l Sincerely, i
Origins! C!:n::d Cy I
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Edward Wenzinger, Chief k!
Reactor Projects Branch 4 i
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Enclosure:
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f bec:with enclosure R. Fuhrmeister's Files RI-91-A-0082 RI-91-A-0084 RI-91-A-0085 RI-91-A-0096 RI-91-A-0099 RI-91-A-0105 l
T. Shediosky S. Stewart E. Kelly a
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Kino CF PRUSSIA. PENNSYLVANtA 19406 M?? 2 -l 1991 l
c This letter refers concerns that you provided to the NRC Region I staff between May 2 and
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May 14,1991. The issues were related to:
l Wiring Diagram for Reactor Cooling Pump RTDs:
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Operability of Steam Generator Mid-Loop Instrumentation; t
e Seismic Qualification of Pressure Instrument for Service Water Supply to Emergency Diesel Generators; Inoperability of Stack Radiation Monitor Due to Flooding and Isolation:
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i Failure to Isolation the Condensate Polishing Facility Waste Neutralization i
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Sump Per Procedure; and, Restoration of Radiation Monitor and the Associated Sample Pump for the
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Waste Neutralization Sump.
Attached are the issues as we intend to characterize them to the licensee. Should you have l
any further questions, or if I can be of further assistance in this matter, please call me collect ;
at (215) 337-5225.
l' Sincerely, l
.l
.l W
kA Edward Wenzmger, Chi'e '
j Reactor Projects Bran l
.p Ir:b natica in this n :d z.:: :...:.1
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Enclosure:
As stated in ac= dance viith the in& cf :n':.'mation i
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l R. Fuhrmeister's Files RI-91-A-0082 RI-91-A-0084 RI-91-A-0085 I
RI-91-A-0096 RI-91-A-0099 RI-91-A4105 y)
T. Shedlosky
/f fl S. Stewart-i m
j F. Kelly
ENCLOSURE I
issue 1:
The wiring diagrams inwhing Reactor Coolant Pump RTD circuits have not been updatedfollouing modifications made under a PDCR to replace RTD circuit kmfe switches with Weidmuller Test Blocks. Drawing No. 25203-31069, Sheet 5, Rev. 3, dated August 29,1989, does not reflect the changefor at least 4 RTD circuits (TCD, TCC, TCA TCB). The instmment loop diagrams (Drawing No. 25203-28500. Sheets 140 & 146) show the Weidmuller Test Blocks. Al:0, in Drawing number 25203-31069, Sheet 5, thejumpers shown betueen cable lead 1 and the cable shield ground on the loop diagrams are not shoun. In addition, access to the GRITS system, to venfy 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 instrwnentation (L-122) was not ' operable" during drain-downfor tube inspections on May 2,1991. GEM suitches werefound to be ' frozen
- on in place. In addition, L-112 had an electronic noise problem caused by an improperly installedjumper. Thus licensce commitment that two monitors be operable during drain down condition was not being met.
Request 2:
Please discuss the validity of the above assenions. If any discrepant conditions are identified, please discuss any actions taken or planned to correct these deficiencies.
Issue 3:
Pressure indicating instrument (P16350 A/B and P16351 A/B) and mountingsfor service water (SW) supply to emergency diesel generators (EDG) are not seismically mounted. Any kind of shock uvuld be suficient to knock the gauge and valve ofof the strainer. Additionally, the location of the taps as shown on the P&lD apparently does not coincide with the actual rap locations.
Request 3:
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Please discuss the validity of the above assertions. Please provide any actions taken or planned to ensure that seismic requirements for these instruments are being met.
i Issue 4:
On May 3,1991, the Unit 2 Stack Radiation Monitor (RM 8132) was inoperable as a j
i result of beingfooded with unter. This monitor uvuld hase been inoperable anyway, as airpow had been isolated. Filling and oressure testing of Steam Generator (SG)
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- 1 uns underway during the same time period. Problems with valve line-upsfor the rad monitor and the SG testing contributed to theflooding and monitor inoperability.
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Additionally, health physics (HP) corarols during remosal of the waterfrom the monitor uns inadequate resulting in contamination ofpersonnel.
j Request 4:
Please discuss the validity of the above assertions. If discrepancies are confirmed, l
please discuss actions that you have taken or will take to ensure that plant procedures regarding rad monitor operation, conduct of tests, and HP activities are being used j
properly.
issue 5:
Procedure discrepancies exist between OP-2336E and SP-2617A for the restoration of the line-up of the radiation monitor (RE-245). and its associated sample pump.
Operators routinelyfail to perfonn OP-2336E, Section 5.1, Step 5.1.13 which is to immediately close AOV-244A/B and AOV-245 when securingfrom condensate l
polishingfacility discharges. Thisfailure tofollow procedures results in 11w sample pump to radiation monitor (RM-245) continuing to operate when the tank discharge
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is secured.
Request 5:
Please discuss the validity of the above assertions. If any discrepancies are identified, please discuss any corrective actions taken or planned, to ensure operators are meeting procedural and technical specification requirements.
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E Issue 6:
Thefollowing discrepancies han been idennfled during an evaluation of Work Order A %&M2-91-01411. These discrepancies idennfy continued non-compliance with procedures and poor response 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 c.
lewi (TK-11).
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The ' Low Flow" switch does not aincys see a lowpow condition when TK-10 i
and TK-11 discharge j, umps stop. The head of water in the pipe and tidal conditions afect thepow of unter.
Operations normally rely on the 15% tank level pump trip to stoppow causing c.
a lowpow to trip shut RE-245 discharge valve, and AOY245. IfAOV-244A/B are shut and no lowpow condition exists, RE-245 sample pump will continue l
1 to run until AOY245 is shut.
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Changes to OP-2336E were idennfied in 1989 to prevent the problems idennfied by AWO-M2-91-04411. However continued identified procedure non-l compliance by operations has caused repeated problems.
i Request 6:
Please provide an assessment of the above discrepant conditions. If the discrepancies o
are true, please discuss any corrective actions that are being used to correct the problems.
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UNITED STATES Ig NUCt. EAR REGULATORY COMMISSION
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475 ALLENDALE ROAD KING OF PftUS$4A, PENNSYLVANIA iMOS AUG 0 61991 This letter refers to. concerns that you provided to us April 13, 1991, alleging:
on Gammametrics procedures are(1) acceptance criteria.for unclear; (2) troubleshooting did not consider EQ checks; thermocouple
-j difficulties with audio monitoring system on pre)ssurize(3 troubleshooting!
valves; and, (4) nuclear instrumentation inoperability. r safety t-We have initiated action to have the Northeast Utiliti review your concerns.
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characterize them to the licensee. Attached are the issues as we inten results of their review.
We will inform you of the i
Should you have any further questions, assistance in these regards, please call me collect ator if I can be of further 1
5225 (215) 337-I h
S cerely
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Edward We zing hief I!
Reactor Projec ranch 4
Attachment:
As stated.
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LIMITED DISTRIBUTION - NOT EDR-PUBLICI)lSCLOSURE v
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Procedures being issued in the I&C department are inadequate in that acceptance criteria are j
not being established for required measurements. Specifically a draft copy of procedure IC 1
2416G was provided for review and it had not incorporated several comments that were -
raised on previous revisions. These comments included: 1) An acceptance criterion for the 1
output of the pulse height discriminator was not established; 2) A precaution was not added l
to check the power supply output of the NLW-3 drawer if the Gammametrics power supply i
drops below 15 volts; The Gammametrics and NLW-3 drawers share the same power supply and the Gammametrics output acceptance criterion is 15-1.5 VDC while the NLW-3 ot@ut acceptance criterion is 15 i 0.0075 VDC, Therefore the Gammametrics drawer may be in j
speciDeation while the NLW-3 is out of specification; 3) The proposed acceptance criterion j
for the discriminator bias voltage was inadequate at.9 1 VDC; Gammametrics recommends 0.8 to 1.0 VDC.
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In addition PORC meeting 2-89-123 authorized change No. 3 to procedure IC-24171-1. The -
change authonzed new settings for NLW-3 drawer discriminator voltage. Section 5.4 of j
IC-24171-1 should have also been changed at this time, and a discussion section on NLW-3 discriminator settings should have been added.
Request 1 Please discuss the validity of the above assertions. Was the procedure released for use, and if -
so, was it unusable in this Geld? Please state whether or not the procedural changes were required to satisfy regulatory requirements, and discuss the review process for procedures and how comments raised during the procedure review are addressed.
1!l Issue 2 While troubleshooting a disabled ICC thermocouple, it was noted that a Litton-Veam connector used to perform the troubleshooting was identical to what is installed in the ICC i
system. The connector used for the troubleshooting was obtained from the NNECO
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warehouse and was not EQ. Work order AWO M2-90-13287, used for the troubleshooting, i
did not reference procedures IC 2421C and IC 2821E, which provide guidance to personnel for working on Litton-Veam connectors that are EQ. I&C department supervisors were i
unaware that this section of the ICC system cabling was EQ. Also the loop folders which were being used for this work were out of date.
a Request 2 q
Please discuss the validity of the above assertions. If valid, please discuss actions taken to ensure that EQ requirements were met in this case.
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. LIMITED DISTRIBUTION _ NOT FOR PUBLIC DISCLOSURE j
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bec w/encit W. Raymond, SRI, Millstone i
Allegation File, RI-91-A-0079 turnover, 0082 (update only)
J. Stewart T. Shediosky b6 6 A m,&G M Ge A
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