ML20044C362
Text
U p
AUG 0 61991 This letter refers to concerns that you provided to us on April 13, 1991, alleging: (1) acceptance criteria for Gammaretrics procedures a:e unclear; (2) thernocouple troubleshooting did not consider EQ checks; (3) troubleshooting difficulties with audio monitoring system on pressurizer safety valves; and, (4) nuclear instrumentation inoperability.
We have initiated action to have the Northeast Utilities staff review your concerns.
Attached are the issues as we intend to characterize them to the licensee.
We will inform you of the results of their review.
Should you have any further questions, or if I can be of further assistance in there regards, please call ne collect at (215) 337-5225 Sincerely, Origid 3 # ed OY Edward Wenzinger, Chief Reactor Projects Branch 4
Attachment:
As stated.
Id:!ma;, "n
'3 2;t0 drcg ;,.g g"I 5s0 ih,; fr.-
.y 'OS C 'i::
lic t, pp~,.y _ r 4:0;:
}
.cfh.<,, _,!.:a ns
~
.a 2-p
~
9303220337 921217 PDR FOIA HUBBARD92-162 PDR
. 's O a
i t
[
r bec w/ encl:
W. Raymond, SRI, Millstone Allegation File, RI-91-A-0079 turnover, 0082 (update only)
J.
Stewart T.
Shedlosky f
/
o
[
4 c
M%
b6 i
i RI:DRP RI:DRP RI:DRP' RI:DRP I RP t
L m
r, 4%$
Tfye/ Stewart Kelly W zinger Wiggins ehl f
I 7///N /
6
j [*%
c rk UNITED STATEE 4 *
,3, NUCLEAR REGULATORY COMMISSION i
)-
.U REOM)N I 3
i 4M ALLRNDAtt itOAD -
t KING OF PRUSSIA, MNNSYLVANIA 1H00 j
AUG 0 61991 This letter refers to concerns that you provided to us on April 13, 1991 alleging:
acceptance criteria for
^
Gammametrics pr,ocedures are(1)unclear; (2) troubleshooting did not consider EQ checks; thermocouple difficultics with audio monitoring system on p(re)ssurizer safety
~
3 troubleshooting
(
valves; and, (4) nuclear instrumentation.inoperability.
Wo have initiated action to have the Northeast Utilities
{
review'your concerns.
staff I
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 5225
}
(215) 337-S cerely l
b 1
Edward We zing
.hlef Reactor Projec ranch 4
'(
Attachment:
As stated.
i f:
i fnformaton in fhb rc:e,,3 e<g ACl txcmpRns _ _in accordan:e rath th Fride c.' Mr fi ff Fol4- -fy,.
7,._' ' ~
)
?
-w c.
n I.IMITED DISTRIBUTION <NOT FOR-PUBLIC e
v IssueI v
Procedures being issued in the I&C department are inadequate i 2416G was provided for review and it had not e criteria are ce ure IC raised on previous revisions. These comments included:
a were
- 1) An acceptance criterion for the to check the power supply output of the NLW-3 draw a e drops below 15 volts; The Gammametrics and NLW-3 drawers share tl i
and the Gammametrics output acceptance criterion is 15 i 1.5 V me power sdpply acceptance criterion is 15 i 0.0075 VDC, Therefore the Gamm
- output specification while the NLW-3 is out of specification; 3) The prop en for the discriminator bias voltage was inadequate at.9 erion recommends 0.8 to 1.0 VDC.
1 VDC; Gammametrics change authorized new settings for NLW-3 dra e
I-1. The IC-2417I-1 should have also been changed at this time, and a discuss
. Section 5.4 of discriminator settings should have been added.
on on NLW-3 Request 1 Please discuss the validity of the above assertions. Was the proced required to satisfy regulatory requirements, an or use, and if s were how comments raised during the procedure review are addressed j;
ocedures and
'i l
Issue 2 t
While troubleshooting a disabled ICC thermocouple, it was noted that a t
1 system. The connector used for the troubleshoot on-Veam I
e warehouse and was not EQ. Work order AWO M2-90-13287 1
did not reference procedures IC 2421C and IC 2821E, which provide used for the troubleshooting, for working on Litton-Veam connectors that are EQ. I&C departme ce to personnel
(
unaware that this section of the ICC system cabling was EQ. Also the l 4
v sors were i
were being used for this work were out of date.
which Request 2 i
Please discuss the validity of the above assertions. If valid, please disc 4
ensure that EQ requirements were met in this case.
ons taken to l
LIMITED DISTRIBUTION - NOT FOR PUBLIC DISCLO
-l v.
m.-
v I
I I
i 4
.y
1 9
i i
- i i
i Issue 3 E
i Recently, a PDCR which installed an audio monitoring system on t!
valves was authorized. The audio system did not contain a spare ey i
PDCR drawing. Also the wire hookup in the PDCR showed two di!
e problems caused the job to be delayed resulting in excessive radiatio
. These workers.
i Request 3 Please discuss the validity of the above assertions. If valid, please di}
to ensure that procedures are technically correct prior to performance and s used i
are performal to ensure worker radiation exposure is minimized.
what preparations
't Issue 4 On April 22, 1991 the "B" and "D" battery chargers were removed from their norm l supply. Later, a technician performing a surveillance on the "C" train a power placed the instrument into Test due to a spiking problem. This act of nuclear instrumentation inoperable. Since the plant was in Hot S test, two trains of nuclear instrumentation were required to be operable I
e Report (PIR) was initiated to document the occurrence but the PIR was late
. A Plant Incident upon an interpretation of the Technical Specification requirements.
celed based Request 4 j
Please discuss the validity of the above assertions. Please discuss the not to document the occurrence, if substantiated, with a PIR.
ecision
+
l 0
i i
i i
i i
n 4
r-4 bec w/encle W. Raymond, SRI, Millstone Allegation File, RI-91-A-0079 turnover, 0082 (update only)
J. Stewart T. Shedlosky i
ec Ier,1)fS M 6 la d ' s > M L
N
'l i
i J