ML20080K564
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NORTHEAST UTILITIES cene.o Ovi.ces. seioen sireet. seriin. Conn.ci.cui
$.7 '.4.52.SY.C P O BOX 270
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HARTFORD. CONNECTICUT 061410270 J !$2[ k,U'*l.',2, (203) 665-5000 k
L October 16, 1991 8
Docket No. 50-336 A09829 Re:
imployee Concerns Mr. Charles W. Hehl, Director Division of Reactor Projects U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Hehl:
Millstone Huclear Power Station, Unit No. 2 RI-91-A-0210 We have completed our review of an identified issue concerning activities at Millstone Station. As requested in your transmittal letter, our response does
}
not contain any personal privacy, proprietary, or safeguards information. The material contained in this response may be released to the public and placed in the NRC Public Document Room at your discretion.
The NRC transmittal letter and our response have received controlled and limited distribution on a "need-to-know" basis during the preparation of this response. Additional time in which to respond to this issue was granted by the Region I Staff in r, telephone conversation on October 2, 1991.
ISSUE 210-2:
" Circuit changes had been made to the Millstone 2 main generator hydrogen monitor without the preparation of a modification package. As a result, the calibration procedure is inadequate, and appropriate procedure and drawing changes have not been made."
REQUEST:
"Please discuss the validity of the above assertion.
If the above conditions are valid, please notify us of the corrective actions you have taken to prevent recurrence.
Please provide us with an assessme.it of the safety sigoificance of any identified deficiencies, including any generic considera-tions."
RESPONSE
This assertion is valid in stating that procedure changes were not made.
There is no step-by-step procedure for the calibration of this monitor.
For the majority of balance-of-plant (B0P) inst: umentation, calibrations are f
8 9503010175 940009 I
- dr. Charles W. Hehl A09829/Page 2 October 16, 1991 performed based on loop folder and vendor technical manual information.
The procedure that addresses the calibration of the BOP components contains There is generic information only and lists the instruments to be calibrated.
specific step-by-step procedural guidance for the calibration of the main no generator hydrogen purity indicator.
- Instead, the technical manual for the main generator hydrogen purity indicator (GEK 4674A--One Cell Thermal Gas Analyzer Equipment) provides calibration guidance for this model thermal gas analyzer.
The technical. manual also identifies the need to initially modify the circuit design to allow the optional use of a remote meter.
As Hillstone Unit No. 2 has such a remote meter, it is likely that this was done during the initial installation activity.
It would not be expected for vendor manuals to have been revised with this information at that time.
This concern was identified to the Millstone Unit No. 2 I&C manager in late July 1991 and responded to within 2 days. During a work assignment, the need for specific procedure guidance was identified and discussed.
The instrument specialist assigned to the task thought that a ste-p-by-step procedure was needed.
He also felt that changes may have been made and not properly docu-mented.
The work activity was stopped before any calibration efforts were undertaken. The 1&C manager's response indicated that a procedure would be developed and any documentation deficiencies wnuld be addressed.
This verifi-cation and modification of the documentation will be a department activity carried out as part of the procedure upgrade progran and is expected to be completed in 1992.
The lack of a step-by-step procedure for the main generator hydrogen purity indicator does not compromise nuclear safety. The existing vendor manual instruction contains adequate guidance, and the monitor performs no safety related function. No modification deficiencies or generic issues have been identified.
We appreciate the opportunity to respond and explain the basis of our actions.
Please contact my staff if there are further questions on any of these matters.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR:
Edward J. Mroczka Senior Vice President jdhdu BY:
J: F_. jpe ka' )
Executive Vice President 1
W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 cc:
E.
C.
Wenzinger, Chief Projects Branch No.
4, Division of Reactor Projects E. M. Kelly, Chief, Reactor Projects Section 4A J. T. Shedlosky, U.S. Nuclear Regulatory Commission, Millstone I
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April 7, 1989
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Mr. Donald E. Moody f
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, Station Manager New Hampshire Yankee Division
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S5abrook Station-g P. O. Box 300 Seabrook, New Hampshire 03874
Dear Mr. Moody:
in Maintenance After a comprehensive review of Namco's ihvolvement Training, Maintenance Procedures and Maintenanc requirements, Namco no longer recommends maintenance teardcwn an replacement of parts in its nuclear qualified limit switches.
In keeping with this decision, Namco will no longer supplyThe Top Cove maintenance kits with two exceptions:
and O' Ring Replacement Kits for Connector / Cable Assemblies.
This, action is effective ilnmediately.*
Namco Selieves it is in the best interest of the operators c' nuclear Narco has found poser' gen'er,ation plants as well as Namco to do so.it com In the long term, to support the maintenance of its limit switches.this decision in their overall maintenance programs.
1; should the end of the qualified life of a given Namco product,The be replaced with a new and identical qualified produ::.should he cenzu:.te1 for At apprcpriate Namco Qualification Test Report in cuestic..
the qualified life of the product Namco wishes to assure you that it will continue to of f er a full line of qualified limit switches and connector seals.
the people who have a need to know within your organization be advised of this change in Namco's operating policy.
We ask that Ver' truly s,
7E. L. Roob Product & Marketing Manager Industry Products ELR/ msg AsvACAdfC.EVC.M c CCm8'* M l
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TO:
Bob Rowe.
MP2 Maintenanc Super or s
f FROM:
ohn H m reys MP2 Maintenance
SUBJECT:
ASCO Solenoid Valves and Namco Limit Switches
REFERENCES:
- 1. ASCO Service Buitetin, Discontinuation of Rebuild Kits for ASCO "NP" Series Valves, Dated May 23,1989
- 2. Namco Letter. E. L. Roob to Donald E. Moody, Dated April 7,1989 References (1) and (2) indicate that ASCO and Namco will no longer support general tear down and replacement of component parts for their solenoid valves and limit switches. In keeping with this change in philosophy, I recommend the following:
1.
MP 2720S - ASCO Solenoid Spare Parts Kit installation (EO), be revised to delete information concerning installation of the spare parts kits. The proce-dure should 3rovide instructions for SOV replacement and replacement of the SOV coi 2.
MP 2720R1 - Namco Limit Switch Maintenance (EO), be revised to delete information concerning installation of the various spare parts kits. The pro-gg O*
cedure should address limit switch inspection, replacement and installation of top cover gaskets.
3.
The PMMS data base for ASCO solenoid valves be completed and sufficient quantities of spare coils and solenoid valves be ordered and placed on re-peating requisitions.
4.
The PMMS data base for valves with Namco limit switches be completed and sufficient quantities of spare limit switches be ordered and placed on repeat-ing requisitions.
Attached is a list of ASCO solenoid valves and Namco limit switches that was prepared by Chris Ferris. The list may not be complete, but at least it [s a start. Dave Knopf is providing a list of Cat 1 and EEQ solenoid valve BOMs for verification.
cc:
J. Riley J. Scheeler r
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SAMPLE RECORD OF ALLEGATION PANEL DECISIONS h5 C
PANEL ATTE DEES:
SITE:
ALLEGATION NO.: 87 )f-4 o219 Chairman -
IeM l DATE: 734kMi (Panel No.$2 3 4 5)
Branch Chief -
PRIORITY: High @
Low Section Chief (AOC) - /elh
- SAFETY SIGNIFICANCE: Yes No @
Sr. Allegation Coord (SAC) Eu loemh-l CONCURRENCE OI Reoresentative - C. (Ab e_
/kolerse CONFIDENTIALITY GRANTED: Yes @
(See Allegation Receipt Report) l IS THERE A HARASSMENT / DISCRIMINATION Yes h ISSUE:
i l IF YES,
- I) has the individual been informed of the DOL l
process and the need to file a complaint within 30 days Yes No l 2) has the individual filed a complaint with DOL Yes No-
- 3) has a letter been sent to the complainant seeking Yes No i
any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:
Yes @o IF YES, HAS IT BEEN SENT Yes No l HAS THE LICENSEE RESPONDED TO THE CHII LING EFFECT LETTER:
Yes No 1
ACTION:
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NOTES:
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SAMPLE RECORD OF ALLEGATION PANEL DECISIONS N5 C
PANEL ATTE ES:
SITE:
ALLEGATION ? O.: 8I-91-4 ot d Chairman -
I l DATE: n AwM (Panel No.6)2 3 4 5)
Branch Chief -
PRIORITY: High @i Law Section Chief (AOC) - &lelli No h Sr. Allegation Coord (SAC) Iuhmh l SAFETY SIGNIFICANCE: Yes l CONCURRENCE OI Reorese atative - e. Ai..e i
TO CLOSEOUT: DD, BC j (Other) bdusa CONFIDENTIALITY GRANTED: Yes (See Allegation Receipt Report) i IS THrRE A HARASSMENT / DISCRIMINATION I
ISSOE:
Yes h l IF YES, i 1) has the individual been informed of the DOL Yes No l
process and the need to file a complaint within 30 days 1 2) has the individual filed a complaint Yes No i
with DOL i 3) has a letter been sent to the complainant secking Yes No I
any safety concerns l 1$ A CHILLING EFFECT LETTER WARRANTED:
Yes @o Yes No l IF YES, HAS IT BEEN SENT l HAS THE LICENSEE RESPONDED TO THE CHILLING Yes No EFFECT LETTER:
ACTION:
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MEMORANNM FOR FILE i
.TELECONk. BLANC [te*D.
DEMPSE*!: Augue:.' 4 1991 ? 9:10 a.m.
t h.
Blanchfcalled me regarding an alie ntien which c:ncerned ppendin R instrumentation pcwer supplier at Millstene 1.
- r. Blan:ogstated that the allegatie:1 is in errer in that tnere are no Appendi:: R audit problems aerocia:ed with instrumentation power has been arrigned a inst rument at ion. Mr. projectBjeneg supplies cf which he is aware.
He dealing with Regulatory Guide 1.97 made the following pointe:
NUSu'O hae identified nc saf e r:-
- r nen-e:=pliance issues associated with hG 1.97 at this time.
Hewever, there are questions associated with lack et redundant p wer eupplier to LPCI and CS flow instruments which are being addressed, among others. on a priority basis. (Instrument AC power supply--single shared *creaker)
-- By original design littje manual c;erator actien was required tc.
operate LFCI.'C5 rystems during design baeis events.
Hence, a common power supply wa: ryecified.
dinre the a.went cf LFCI hest e::chan c er
- Jew 1dmite.
nev and hiper
- cr
- -a :iden:
terue temparaturee, and revision 4 E0PS, opera::re new rely more on tnere j
flow instrument.s to guide manual actions.
Hence, reaundant power rupplier may-be appropriate.
LPCI/C5 flows are not Type A variacier at :nis time.
They are being reevaluated at this time.
The focus of the RG 1.97 proje:: g er beycnd the c:mpliance issue te tnat of the ability ei the sytreme tc perform the safety runcticn given the' worst single railur+.
A.- re ert operability determination (PEF) resulted in a finding that the systems were operable.
Blanchelso discussed briefly tne recent unusual event at r.
Millet:ne which involved lora of emergen y asseecment capability.
During the hurricane, the Perlin computer mainframe wss loet resulting in dumping o f, dese assessment
- formulas, weather information.
- OFIS, etc.
He indicated that there was acme EOF to declara t UE since backup At any re.te.h_.heBlaneptatedthat resistance a*
the corporate methode supposedly available.
management le giving the computer issue appropriate attention now.
P ASSESEMENT:
There - are no new allegations.
The purpose of the conversation was to clarify informaticn previ:uely identified t:
NRC.
t Allegation item number 5 : f August 14. 1991 0 1300
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V-w ALLEGAT-ION MANAGEMEHT SYSTEM g jALLEGATION NUMBER'- RI-91-A-0219-RUN DATE: 09/11/91 m;..
?fEADOCKET/ FACILITY / UNIT: 05000336 / MILLSTONE 2
'/ 2 DOCKET / FACILITY / UNIT: 05000245 / MILLSTONE 1
/ 1 DOCKET / FACILITY / UNIT:
/
/
DOCKET / FACILITY / UNIT:
/
/
. ACTIVITY TYPES - REACTOR MATERIAL LICENSES -
I OPERATIONS i
FUNCTIONAL AREAS l
DESCRIPTION - 1)
VENDOR INFORMATION RELATED TO EQ MAINTENANCE (NAMCO SWITCHES AND VALVES) NOT INCORPORATED IN TIMELY MANNER 2)
EOF DIESEL LOAD TEST PROCEDURE INADEQUATE AND NOT l
CONCERNS -
PROPERLY IMPLEMENTED.
i 3
3)
NO REDUNDANCY EXISTS FOR APPENDIX R POWER SUPPLIES FOR UNIT 1 (ASSOCIATED WITH INSTRUMENTATION)
SOURCE - LICENSEE EMPLOYEE CONFIDENT - NO
[
i RECEIVED - 910814 BY - PJ HABIGHORST
/ RI i
(FTS)346-5183 ACTION OPFICE CONTACT - EM KELLY SAFETY SIGNIFICANCE - UNKNOWN BOARD NOTIFICATION - NO l
STATUS - OPEN SCHED COMPLETION - 911231 DATE CLOSED -
l ALLEGATION SUBSTANTIATED -
ALLEGER NOTIFIED -
OI ACTION -
OI REPORT NUMBER -
REMARKS - ALLEGER PROVIDED COPIES OF INTERNAL MEMORANDA AND PROCEDURES l
TO SUPPORT HIS CLAIM.
PANELED 23AUG91.
t I
i SUPPORT OFFICE:
RPS-4A ACTION PENDING:
REFER TO LICENSEE
}
DOCUMENTATION:
ALLEGER LAST CONTACTED:
14AUG91
REFERENCE:
l KEYWORD:
PROCEDURES i
ENTERED S** STEM - 910822 CLOSED SYSTEM -
RECORD CHANGED - 910823 j
r i
l
- y' of fflf Offff/
O
{l issue 91-219-01 l
Changes to vendor maintenance and surveillance instructions are not evaluated and needed procedure changes are not being made in a timely manner. In particular, MP i
2720RI, NAMCO Limit Switch Maintenance (EQ), references NAMCO EA 189-90051 g
(December,1980) whereas the vendor has superseded EA 189-90051 with EA 189-90060 l
(February 4,1991). This new information warns that removal of the bottom cover of V
the limit switch will negate the qualification (EEQ). In addition, NU was notiGed in May,1989 that the vendor would no longer support re-work and spare part kits for their c'
solenoid valves and limit switches. The concern is that key craft personnel are not aware of these changes.
- Issue 91-219-02
\\
N si MP 2722B, Annual EOF Diesel Generator Load Run, is dcDcient in that the division of work responsibilities among electricians, mechanics, and contractors have never been evaluated as appropriate. Further, AWO M2-89-09594,.ar the annual load test, does not reference MP 2722B or the other controlling procedure, EPIP 4303, and, there appears to be the following discrepancies in the drawings associated with the te t:
[/
1)
Electrical circuit breaker positions on electrical pane!s'XLP1 and KLP2'do not agree with diawing 25205-30007. Circuit breaker No. 261s i~n question on L
ELPl; breakers 10 and 12 are in question on ELP2; i
~I l
p 2)
An electrical remot:: control panel,(
l is shown on drawing 25205-30007; but I
f, does not appear to exist; 3)
The schematic portion of drawing 25205-39002, sheet 3 (or 25205-32008) appears incorrect and is confusing; j
4)
A utility plug is located at the bottom of the electrical power distribution system automatic bus aansfer device (ABT). This conDicts with drawing 25205-32008; 5)
The vendor representative and mechanic involved with the annual load test of the EOF emergency diesel generator are not qualified to perform the electrical 1
portions of the test; and, 6)
The review of procedures made by PORC is inadequate.
Rec]uest:
Please discuss the validity of the above assertions. If any denciencies are identined, please provide us with the corrective actions you have taken to prevent recurrence.
Please provide us with an assessment of the significance with regard to safety of any identified denciencies.
tiMFED-DTbOOPWNUT L
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MILLSTONE POINI LWii 2 i
EQ MASTER LIS1 j
FE'llSION NO.
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i icrted by Cceper.tr.t '#t (10 QUAL EQ FLANT 10 NO COMf0NENT T1FE 20NE MAWFAti'JER MOCE NUM5ER flLE LEVEL NOTES 15-6731 (1)
LIM!i 5 WITCH A-2 NAMCD EA7:0-20100
-125 0586 Viv fB-66.le A
25-6731 (2)
LIMIT SWITCH A-2 NAMC0 EA740-20100
-125 0588 VivFB-68.lA 15-67 5 ill LIMIT SWITCH A-3 NAMCO EA710-20100
-125 0588 hv st-n.tr M Viv Ei-68.16 15-6715 i'l LIMli SiliCH A-3 NANCO EA740-20100
-125 0588 ~Viv Fru-4X 3 15-7311
( )
LIMIT SWliCH A-18 NAMCO EA-740-20100
-125 0588 15-7312 til limit SWi1CH A-17 NAMCD EA-740-20100
-115 0588 Viv 51-312 25-731:
(2)
LIMli 5 WITCH A-17 NAMCD EA '40-20100
-125 0588 Viv $1-112 25-7690 i i LIMIT SWiiCH A-18 NAMCD EA '40-20100
-125 0508 viv t-45 Ng 25-8082 s1 limit SWITCH C-05 NAMCO EA-180
-109 0588 Viv AC-5 14 25-81:1 41)
LIMil IW11CH A-50 NAMCO EA-160-11:02
-109 0588 Viv AC-47 N 25-8121 (2) ilMit 5Wii:H A-50 NAMCO EA-190-lM02
-109 0588 viv AC-47
!5-8122 (1)
LIMil 5WiiCH A-51 NAMCO EA-180-Il302
-109 05B8 Viv AC-12 25-8122 (2)
LIMll SWiiCH A-51 NAMCO EA-180-12302
-109 0588 viv AC-12 IS-8124 til LIMli SWITCH A-Si NAMCD EA-150-11:02
-109 t588 Viv At-15 15-8124 (21 LIM!i SWiiCH A-51 NAMCO EA-130-1302
-109 0508 Viv AC-15
- 5 8125
()
LIMIT SWITCH C-05 NAMCO EA-180
-109 0588 Viv AC-6
- A
- 15-8150 (1)
LIMIT SWliCH C-05 NAMCD EA-180
-109 0588 Viv EB-88
- 5-8150 (2)
LIMIT 5W11CH C-05 NAMCO EA-180
-109 0588 Viv Ei-83
- S-8151 (1)
LIMIT 5Wi!CH C-05 NAMCO EA-180
-109 0588
'viv u-si 25-8151 i:1 i!MIT SWiiCH C-05 NAMCO E:-180
-%9 05B8 Viv Ei-89 15-8:06A (1) limit SWITCH A-2 MICR0 SWITCH i35-4L-6C
-164 D0R
- enr HV-12t IS-8306A Cl LIMll SWITCH A-2 MICFDSWiiCH L5t-4L-8C
-164 D0R Dapr HV-326 h 15-83068 til LIMli SWiiCH A-2 MICR0 SWITCH L;r-4L-8C
-164 DOS Lasr hv-325 15-8306B Cl LIMIT SuliCH A-2 MICR0 EWITCH L58-4L-SC
-164 COE tapr HV-3:5 IS-8IOLC (Il LIMli 5 WITCH A-2 ft!CR0 SWITCH L5r-4L-80
-164 DDR Capr H N ;E IS-8306C (2)
LIMil SWliCH A-2 MICR0 $ WITCH L5f-4L-8'.
-164 00R Depr HV-325 h 25-8;060 (1)
Ll'Ili SWITCH A-2 MICR0 SWITCH L5K-4L-BC
-164 DDR Depr H M 27 15-8!06D Cl LIMli SWiiCH A-2 MICR0SWliCH L5(-4L-3C
-164 00R Csor H M :7 25-8312A til LIMli SWITCH A-3 MICR0 SWITCH L5f-4L-GC
-164 DDR Dear H M it 25-Eil:A (2)
LIMIT SWITCH A-3 MICFDSWITCH L5r-4L-8C
-164 DDR
,Depr HV-314 I5-83128
(!)
LIMll SWITCH A-3 MICR0 SWliCH LST-4L-6C
-164 LOR Depr HV-51;
!5-8;l:B
'21 LIMil SWITCH A-3 MICR0SuliCH 1.5r-4L-2t
-164 00R Csor HV-;l; 5-5;12C (1)
LIMli SWliCH A-3 MICR0 5 WITCH LSt-4L-BC
-164 CDR Dapr H N 15
- 5-81CC Cl LIMli SWITCH A-3 MICR0 SWliCH L5f 4L-8C
-164 DDR Depr HV-315 15-831:3 (11 L! Mil SW11CH A-;
MICR05 WITCH L5r-4L-SC
-164 DDR I,spr W -;to 5-6;l:0 Cl LIMli 5 WITCH A-3 MICR0 ! WITCH L5r-4L-8C
-164 DDR tsor H M it 15-8377 (1)
LIMIT SvliCH F50 NAMCD EA-740-B0000
-125 0508 Viv EB-N IS-8;77 Cl L1811 5W11CH 4-50 NAMCD EA-740-80000
-115 05B8 Vlv EB-99 Q 15-8377 G1 LIMIT 5 WITCH A-50 NAMC0 EA-740-80001
-125 0588 Viv EB-99 IS-B;75 (11 LIMIT 5 WITCH C-05 NAMCO E A-740
-125 0588 Viv Eb-t o 25-8378 (Il limit SWITCH C-05 AAMCD EA-740
-125 0586 Viv EB-lM 11)
LIMli SWITCH A-50 NA9CO EA-740-B0000
-1:5 0558 Viv n-U 25-8;79 (2)
LIMll SWITCH A-50 NAMCO E A-740-80000
-125 0508 Viv EE-92 g 05-5179 15-B379 Cl LIM 11 SullCH A-50 NAMCD EA-740 60001
-125 05E8 Viv EB-C
i NORTHEAST UtillilES SERVICE C00ANY WB i
MILLSTONE F'OlNT UNil 2 EC MASTER LIST PEVISION WD.
2 37ted by Comp 0ntr.t ipe Ig
, EE3 ML FLAMI 10 NO CCMPONENT ITFE ICHE MA40FACTUREE MODEL EMBER ILE LEVEL N3TEi
- " - - ~ " - " " " " " "" - " " " * * * " " * * * "
- " - ---------------~~~--
15 198 til LIM 11 SWITCH A-1B NAMCD
[A-740-20000
-1 5 05B3
?)v EH-lib 9 -1
!$- 198 121 limit SWITCH A-la NAMCO EA-740-20001
-1 5 05EB alv DI-l?3 IS-565 (l
LIMIT SWiiCH A-la NAMCD EA-74 M 0100
-1;5 95BB Viv CH-505
-- IS 06
([ LIMil SWITCH C-05 NAMCO EA 740
-1 5 0558 Viv CH-506 th
'3 '06 (2)
LIMif SWliCH C-05 NAMCD EA 740
-1:5 0558 Viv CH-50s S-515 t1 limit SWiltH C-05 NAMCD EA-180
-109 0558 Viv Di+.5 A
!S-516
( l LIMIT 3W11CH C-05 NAMCD EA-li0
-109 05B8 viv i M 16 y
IS-517 (l
LIMli SWiltH C-05 NAMCD EA-180
-109 0558 Viv Mli 14 15- $1B (l
LIMIT SWITCH C-05 NAMCG EA-180
-109 568 ylv xtb N
!$- 519 (l
Linli SWITCH C-05 NAMCD EA-180
-109 0550 M' EIS N
IS-614
( )
LIMii SWITCH C-05 NAMCO EA-130
-109 0558 Viv si-614
/v
!S-618 (l
limit SWiltH C-05 NAMCD EA-150
-119 0558 Viv 51-618 A
IS-624 (l
LIMil SWITCH C-05 NAMCO EA-130
-109 CSEB ylvSI-624
/\\
!$- 628
( )
Linli SWITCH C-05 NAMCD EA-180
- 1,9 05SB Viv 51-62B A
9l-SL gia 05s3 a v si-6:4
(
!$- 634
()
Linti SWliCH C-05 NAMCO EA-180 t
- "> ^!!?
41v 51-63B IS-638
()
LIMli SWITCH C-05 NAMCO EA-180 q
-109 O!?B Vlv 31-548
'N j IS-644 (l
LIMIT SWITCH C-05 NAMCD EA-180 4
5-64B
( l LIMIT SW11CH C-05 NAMCO EA-180
-109 05EB Viv S1-648 A
S-1060 til LIMli SWIICH C-05 NAMCO EA-74
-1:5 0$EB Vlv RC-005 A/
IS-1060 GI lM]T SWITCH C-05 NAMCO EA-740
- 125 05BB
- N
/
5-1069 (11 LIMIT SWITCH C-05 NAMCD EA-740
-125 0568 M v u-M Cl LIMli SWITCH C-05 NAMCO EA-7:0
-1;5 35ES Viv it-002 b
f'S'106h 23 1064 (1) limit SWITCH C-05 NAMCO EA-740
-125 0508, Viv EC v01
$-1064 (2)
LIMli SWiiCH C-05 NAMCD EA-740
-125 05BB Viv FC-001 b
'lv C& OB9 M
25-2525 (l
LIMIT SW11CH A-18 NAMCO EAlB0-11302
-109 05EB
=
15-C46 (11 LIMll SW!it't A-17 NAMCO EA-740-20100
-125 05BB vlv Mi-229A cp,
g IS-4246 (2) limit SWITCH A-17 NAMCO EA-740-20100
-125 0508 Viv MS-220A 15-4248 (1)
LintiSWliCH A-17 NAMCO EA-740-20100
-1;5 05BB Vlv M5-220E IS-4248 (2)
Linli SW11CH A-17 NAMCO EA-740-20100
-125 0588 ylv M3-220B IS-C50 (l
LIMIT SuliCH A-1B NAMCO EAIB0-11302
-109 05BB flvR3-lilA f*
13-4251 (l
Linli SWITCH A-1B NAMCO EAIB0-ll30:
-101 05BB inv a -liar rs a
- 5-5:76 (1)
Linti SWITCH T-10 NAMCO EAlB0-ll 02
-109 05EB Vi v "-M h
25-5276 (21 LIMliSWITCH T-10 NAMCO EAlB0-ll 02
-109 05BB Viv Fii-'!A 15 5:79 (1)
LIMIT SuliCH T-10 NARCD EAlBO-In30:
-109 055B VlvFW-4:6 i[
Z3-5279 (21 LIMIT SWITCH T-10 NARCD EA100-ll302
-109 05BB Viv FW-43B 25-6050 (11 limit SulTCH A-2 NAMCD EA740-20100
-125 05BB Viv kB-13.lA 25-6050 (21 Linli SWITCH A-2 NAMCD EA740-20100
-125 0538 VlvFE-l!.lA
!$-6080
()
LIMli SWITCH A-17 NAMCC EA-740-20100
-125 05BB
_Viv Ab-B.'A N
IS-6034 (l
Linli SWliCH A-1B NARCD EA-740-20100
-125 OtBB ylvv5-28.ib A lS-6058 (l
LIMll SWITCH A-17 NAMCD EA-140-20100
-G5 05B8 Vi, W. A A 25-609;
()
LIMli SWliCH A-1B NAMC0 E A-740-2010.
-125 0558 liv %-4 t
5-6306 a1 Linli SWITCH A-1B NAMCD EA-lE0
-109 05EB V u w e..'
9 O :!S-6307 (l LIMli SW!iCH A-1B NAMCO EA-180
-lM 05EB r.v *L ib m
!3-6308 4 i Linli SuliCH A-1B NAMCD EA-180
-109 055B VI,
- d.ia (A
s NORTHEAST UTIL111ES SERVICE COMPANY Page 1)
~
MILLSTONE POINI UNii 2 EQ MASTER L l'S i REVIS!~N k0.
S rtu t,y Ccaconent *ype I
EQ EEG ;UAL FLAhi ID *iG C3MPONENT ifPE ICNE MANU~ACTURER MODEL NUMBER FILE LEVEL N01ES 25-8;80 (11 LIMli SWITCH C-05 NAMCO EA-740
-125 0588 Viv EB-91 25-8380 (21 LIMli SWITCH C-05 NAMCO EA-740
-125 0508 Viv EB-91 IS-565e ill LIMIT SWITCH A-50 NANCO EAISO-32;02
-109 0588 Viv AC-20 25-8656 (2)
LIM!i SWiiCH A-50 NAMCO EAlB0-32302
-109 05B8
.Viv AC-2) 15-9015
- 1
limit SWITCH C-05 NAMCD EA-740
-125 0588 Viv LRR-43.1 25-0015 (2)
Linii SWIICH C-05 NAMCO EA-740
-125 0558 Viv LRS-43.1 M 25-9016 it:
LIMil SWITCH A-17 NAMCO EA-740-20100
-125 0500 viv LEit-4;.2 h.
25 90le (2)
LIMil SW11CH A-17 NAMCO EA-740-20100
-125 0588 Viv LEA-43.2 25-9125 til Linli SWITCH C-05 NARCD EA-740
-125 0568 Viv SR-il.1 25-9125 2)
LIMIT SWliCH C-05 NAMCO EA-740
-125 05B8 Vlv 6R-11.1 N ZS-912e
()
limit SWITCH A-17 NAMCO EA-740-20100
-125 0588 Vlv M-II.; %
15-7150 ill LIMli SW11CH A-18 NAMCO EA-740-20100
-125 0588 viv bar-16.4 25-9150 (21 LIMil SWITCH A-18 NAMCO EA-740-20100
-125 0508 Viv SSP-16.2 O 25-9151 til LIMIT SWITCH C-05 NAMCD EA-740
-125 0588 viv dat-io.1 25-9151 (2)
LIMil SWITCH C-05 NAMCO EA-740
-125 0588,Viv SSP-16.1 k 25-9230 (1)
Linti SWITCH C-05 NAMCD EA-740
-125 0588 vle L A-61.1 f 15-9230 (21 LIMli SWi1CH C-05 NAMCO EA-740
-125 0508 Viv LRR-61.1 15-9506 iI LIMli SW!iCK A-52 NAMCO EA180-21302/22302
-109 0588 Caer HV-455 pA 25-9507
()
LIMli SWITCH A-52 NAMCO EAlBO-21302/22:02
-109 0588 har w-4 e6
/A l5-9508 ii LIMil SWITCH A-52 NAMCO EA100-21:02/22302
-109 0558 tapr HV-497 pA.
o
GENERAL FUUll'MENI -H IS1URV REPORT 14. 4.....: ME *1 03032 I
TR NO..: 05M2113953 EQUIPMEHf DESCRIPTION: #I STEAM hENERATOR DLOWDOWN CONTRUL VALVE WuSIEMD. i l}61E _gGMCLUT LD : 08.23/01 PMMS 10:
MI. 02.
STG N'V r ut
.-810 1 OCAl. ID:
It?
".-MS
. : 4 iA LOCAL SYS:
.R 16 kB@ LEU,DEM : V AL'.'E POS I T I ON INDICAinR lit 1IT SWITCH ACTUATOP DOLM Nut 40P6 : PROPERLY. REPEATEDLY HAVE DUAL INDIC AT ION AF TER CYCLING VAL U j
E GUSEC.19 C60$15...:
i URIGINATOR.......: M SANDERS ORIGINATING DEPARIMEH1.: OPS LWlE ORIGINATEI).. : 04/05/91 J.9R_DLiOC_: 1) ADJUST LIMIT SWITCHS ONLY. IF OTHER WORI. IS REQUIRLU CONTACT PMMS FOR A NEW AWO.
CAUPE_OE_EbOOLEU:
I:AILURE col?E:
DEL 6XC_d-.C_9M!1Cl31E:
t>ElAY LODE..:
Jpg_5UfXRVISOB: R BAGOS WOl3
- H PAGOS R CASTLE K PICl.LES C E !i E..E Y :
SPECIAL EQUIPt1ENT..:
SERI AL NUMI:ER...... :
PROJECT REFERENCE..: SDWL11E PROJECT DESCRIPTIOlJ:
PB00EDUBES L6U11995 CAU110tLU21 E PLANr TAG.: Y SIEWS-49-B St~CTION XI IF JOD SCOPE CilANGES, CUtJ :
CONVEX TAG: N CLEWS-50-8 ENGINEER FOR SEC1 ION XI FC EVAL:CD-190 AU CCC ACC SU C CMS W.O.
ACT RE AC%
P.O. NO.:
ACCOUNTS.:
PDCR NO.:
VALVE WORKS FINE 6Cly66._W9EU_4_GE M66[S_f _E6EIS_ygE D e
GI!NERAL EOU1FilENI--His FORY REPnh r
- - U.O.
..: ME 91 08030 TR NO..t 07M?.135031 l'
EQUIPMENT DESCRIPTION: LOOP "ZA" NON-RETURN CHECI'. LEAKOFF DRAltJ 'jTOP V r '.' / E
' I Alpiq0!j[tEjl;D: 08/08/91 PMM3 ID:
f LOCAL ID:
MC C-S I
.:.Mi t LOCAL SYS: Z?OO CBODI, Elj_.t E5C : 1)UEL IMD. ON VALVE WITH TULL CLOSED sir,NAL FROM i
)
CnNTROLLOR.
a Prw 0397c1 RUSEWID (6UgS...:
ORTGINATOR.......: M RADICE ORIGINATING DEPARTMENT.: UPC I> ale ORIGINATED..: 00/07/91 dQI]_DESQ: 1) 1RDLSilOOT DUAL INDICATION.
- 7. ) ADJUST t.IMIT SWITCHES AS I'ECESSARY TO RECTIFY PROBLEH.
- 3) IF FURTHER REPAIRS ARE REQUIRED, RETURN 10 QSD FOR APPROVAL.
i
- 4) PERFORM REPAIRS AS INDICATED NECESSARY FROM TRDLCHOOTING.
i C6MEfi_.gE_Ebgt%Et1: COMMENTS:
WOULD flAVE INSTRUCTED THEM TO PRESS THE RESET AFTER A POWER LOSS.
FAILilRE CODE:
UElAY.S_I..,99tlHEN15: SLICCE55 WAS THWARTED ON FIRST E ENTRIES DLIE TO AWO del #/ CODE.. :
STICl;ER EFING PLACED OVER WARNING TO OPERATORS THAT 10H GUECRylggR: J HEISLER 3
WOBb
- l HEISLER R CASTLE PERF_,By :
GFEC1 AL. EQUIPMENT.. :
NERIAL NUMBER......:
PROJECT REFERENCE..: SDWL11D PROJECT 1)ESCRIPTION:
428070040 i
EBQ(EDUBES (6911Q9@
9691] Qty Ni_tME PLANI FAG.: N 27;OR THIS WORK OF DL'.R IS OSO HE',
CONVEX TAG: N SEEWS-10-A TO ACP-QA-C.16, r G. :7 t. I T' )
EVAL:CD-180 j
ACT RE AC%.
P.O.
I FJ. :
ACCOUNTS.
PDCR NO.:
i
^9190L._BQSE_f_EElj68$Q,_f_E6813_yEEQ :
MADE S ENTRIES INTO CTMT TO TROUBLESHOOT AND ADJUST VALVE, INDICATION.
ON SRD ENTRY ADJUSTED LIMIT j
SWITCH ARM TO GIVE PROPER INDICA 7 ION AND OPS RETESTED AND TIMED VALVE 1
i OPERATION SAT.
NO EEO BOUNDARIES WERE DREAC.HED.
H.U.
..: Mr. a t O'3434
^TR nen..:
?.' M.:.t 1 0 3 t*?
CQUIPMENT DESCRIPTION: LOOP "2A" NON-RETURN CHECI: LEAKOFF DRAIN Sin 00 l.E C OtJ14]I L!: 06/04/9I PNMS ID:
HZ O2 HF I At ti' l'GN _ '. 1 L OC AL ID:
M.~
.f.- M I v i.O LOCAL SYO: 2 ^:00 1,'BhtjjLgt_i_J6'4 : VALVE HAS OUAL INDICAfIGN ON CO-2. PR tt 363G8 i
UUtiCCID G6{JSE...:
UR1GINATOR.......: 5 BAKER ORIGINATItIG DEPARTMEtJT. : UPS DATE ORIGINATED..: OG/26/91
,!ptj_ljESQ: 1) INVESTIGATE AND ADJUST lit 1IT SWI TCHES TO PROVIDE ACCU!-RATE VALVE POSITION NOTE-MAKE ADJUSTMEt4TS ONLY REPAIRS REQUIRE A 3 PAGE AWO I
c.:6UZC_gE_tRgELEU:
i l' AILURE CODE:
l!Ei,6y5_f _GQt_1MEUIS :
D',_AY CODE.. :
dQQ_SWEgBylgGR: R BAGOS WORT;
- T O'SULLIVAN B STANGLE EERE_DY :
SPECIAL EQUIPMENT..:
SERIAL NUMBER......:
PROJECT REFERENCE..: SDWL11B 92G09004 '.'
PROJECT DESCRIPTION:
i ESQCEDUEES C6911QNe C;GUfIM(LUOE Pl. ANT TAG.: N 2701J-40 l
CONVEX TAG: N 2700D2 l
2720R AU CCC ACC SU C CMS W.O.
ACT RE AC7.
P.O.
NO.:
?2 PDCR NO.:
ACCOUNTS.:
CYCt.ED THE uALVE 4 1IMES AtlD 691UAL_WQBt;_L_BEM68!IS l_E6BI@_USEQ :
INDICTED CORRECTLY.
ADJUSTED SWITCH.
NEEDS l10RE F INE TUNING.
ADJUSTED LIMIT SWITCH.
E Gl'NERAL t 8.ru l Pl1EN ) III S (ORY hl,l 'Uh l
' c 'J. u...: M2 91 07730 lH NU..s 14H.0144 57 E QUI F hl'N I DESCRIPTION: REAC1OR COOL.Alli PUMPS DLEADOFF tONTRUL Vt9 VE AYEt C
'#~
D.dl.b_.C_f'id O S 1 EI!: OC:/E7 /9 J PMMS ID:
M2 of CV(: Aiv>
_- 'H LOCAL ID:
M.0
C l l-1 M:
LOC /d. SN :! : 03s i4 A I:ljul ! Elj,0ER: GRCH1 LIGHT LIT ON COC W/ VALVE '42 OPEN Wils iUI.D 1:E UUr). l.IMIT SWITCil(ES) NEED ADJUSTING.
r.P. m 16:
JUSECTD cAugE...:
URIGINATUR.......: K NASH ORIGliWI ifIG DEPAR ilIEN I. : OP OATF ORIGINATED..: 07/04/91 4QTj_,1f.SC : 1) ADJUS1 LIMIT SWITCHES TU INDICATE FROcER POSI110N IF LIMIT SWITCHES REQUII;E DISCONNECTING, RETURN PHG TO PMMS/ ENGR.
C6 Veli QE_C60!SEU:
FAILURE CODE:
OEb6YS_/._ggdtjgNIS : GREEN LIGHT SHOULD REMAIN LIT UNITL VALVE'S DELAY CODE..:
FULLY OPEN.
J,Q,C1_gyPEEi'l@OR : R BAGOS f
IJQBG
- R BAGOS R CASTLE CE6E._EY 8 SPCCIAL EQUIPMENT..:
SERIAL NUMBER......:
PROJECT REFERENCE..: SDWL11E PROJECT DESCRIPTION:
EBOGEDUBES Q69IlgNS C6y11QU_U91L5 PLANT TAG.: N EVAL:CD-179 CONVEX TAG: N NOTIFY-ENG AU CCC ACC SU C CMS N.O.
ACT RE AC7.
P.O.
NO.:
ACCOUNTS.:
PDCR NO.:
69.T,y6L,_ !!C_iBE_ f_ bed 6 BUS _f _E6 big _yEEQ :
INVESTIGATED PROBLEM, FOUND val.VE TO DE WORKING PER PRINT #2520.3-32009, SH. 30.
GREEN LIGHT SHOULD DE.
ON UNTIL VALVE IS FULLY OPEN.
Qft:
Q' M
ype 3-t PIR INVESTIGATION L
NOT REPORTABLE i
b
^ >
TO:
Brendan J. Duffv j
FROM.
Unit 2 PIR Report Coordinator (Tel. x4423) '
l
- You have been assigned as investigator for PIR 91-117. dated.
I J
\\
This PIR has been initially assessed to be not reportable under 1 FR50.73.
To support the PIR adminstrative routing process, a timely response is l
imperative. The PIR investigation is to be completed by 02/16/92.
1 INSTRUCTIONS FOR PIR INVESTIGATORS
-i 1.
Per ACP-QA-10.01,6.2.4, the assigned investigator shall l
a.
Complete Section 3 of the PIR.
j i
b.
Verify (if applicable) the use of emergency operating procedures and document their review and use.
2.
Ensure that if a PIR is generated due to a failure of any RPS/ESF channel -
on a quarterly test program, that an evaluation for a common cause mode i
will be performed under the ICR program IC 2437A.
3.
Section ill of the PIR must be filled out in its entirety. All PIRs that require PORC approval must be reviewed by the appropriate department head prior to PORC presentation.
4.
Particular attention should be payed to identifying correctly the root cause of the event. The root cause may be defined as "the cause which, had it been prevented, would have prevented the event."
]
NOTE: If, during the course of your investigaiton, you determine that this event may be reportable, notify the Unit 2 Operations Manager or Duty Officer.
5.
Forward the completed PIR investigation to the report coordinator.
cc:
LER Coordinator. S. E. Scace. R. J. Factora. S. M. Temole
__. _. _. _. _.. - _. -. _. _ _ - - ~ _ _ _. _ _ _. _ _ _ _ _ _.. _
4
/-/kk' 9/-09
/P p1(
fcci -
FOAM APCAOVETBY DIRECiOR. MILLSTONE STATIONE*FE'CTIVE DATE SORC MTG. NC
/ftJ/
No; 9/-// Z,
PLANT INCIDENT REPORT - PART A Report Date: //
/O[J/!/ /
/
INCIDENT TIME
/ [3 (>
1.
PIR INITI ATION INCIDENT DATE 50F DIES *Et.
GEA/GWA7~fd' FAtt uxt=
- 70 4oAh 26F Dissc=t-GEEwexA7FA i~A /L E D Te ACRb At/TrMAT/clY Desenpuon of Event:
buffi A/n syfusiLugMt:-
Eft 1"-'Mo&
JW CCHTAet-C J ACit ir l'ONTAC7*S.
Descripuon of Cause utk.nown 1
1 l
hsstem Alteciec-hvstem Nurit'er:
PMM5 ID Nufnner:
.Name at inmaior:
hi~
tur -
20/*
NIA N/ff Th N)00h'U MM p -
11.
PLANT INFORM ATION PowerFe s :
Temp Pressure:
Plant Condmons Moce.
l Descnotion of Inmal Action; Nf f) FI L=b NIA/NrANAfCE J]A(jffff
/'/ tL!Ef(
fntt 7' At'A/L A Rt2 C
0 i
Safets implicat ons: E(-)C~
Secursts implicauons-N /> A/6 Basis g/1pf. 4/ 7pf. 4f jy l} gy f incicent Category Q A. Immediate
] B. 30-Day LER
] C. Public Interesi 2 D Not reportable to NRC
] D. Fitness for Dutv i
Operauons Manager Notinec
] Yes ] No Name.
Mf Date:
/V g Time: A/ g
' Norma! Houro of A B C f rcident Dut) Officer Nonfied-SYes ] No Name-8, hdff#/
Da /th/k/Tme M8
]
i g!g l $
g[j$
g)/)
T.me Date-SSSA Notified and EPIP all: Nouficauons Mace.
] Yes $Ne Name Date: N$
Tm.N[A N[4 Securiis Shift Sueerusor f Potentia: Securtis Threatt: ] Yes ) No Narne-Snit: Sep
'Da :
Prosecures Lsec,_
a w
F 111. INVESTIG ATION INFORM ATION Personnel Quesuennaires Attached
% Yes ] No List: f.$(#44CATLr[
t' de N6ffL6/Y Procecure CnangehA/g
) T es
_J No y
Trouble Reoorts Subminee Phoiographs: ] Yes % No Maierial Being He;d-
]Yes JNo Locanon
/$
AWO Cop., a ttached
] Yes ] Ne Safet) Tag Sheet Cop > Atisched, J Yes ] No 6
Signat Date; j
informauon Gathered v:
l IV.
DUTY OFFICER REVIEW Immediate investigation Necessars:
Yes ] No
)
[
////
/
' I
/
l/ % V {,)
V.
UNIT DIRECTOR Assigned incident Category: DA Os DC @ DE OPSSH Remarks:
PORC Reuem
] T e-M No NRB Reuem -
3'ie. S.No NEO : ! Ininaied 3 i e* dNr Lnu Director Date:
Inse*ugaior A, signed f g))
7 Ref: ACP-QA-1kok SF 1001 Rev.9 Page 1 of 4
PLANT INCIDENT REPORT - PART B PERSONNEL QUESTIONNAIRE NAME POSITION (PRINT)
PLANT EVENT TITLE f'
EVENT DATE/ TIME PIR ND1BER (IF KNOWN) 1.
Desenbe the event:
i I
i 2.
When did you know there was a problem, and how did you find out?
I I
3.
What were your acuons?
i 1.
What could be done or changed to prevent this problem from happenmg again?
i i
i 5.
Any other information you consider important:
j i
Signature Date Time j
Supervisor Signature Date Time Ref: ACP-QA-10.01 SF 1001 i
Rev.9 Page 2 of 4 APR B 1991
- )
?
PLANT INCIDENT REPORT - PART C Report No.
9/-// 7 3 Follow.os twtstic4Tios.ciscLE cNEt i
I. PIR INVESTIG ATION f Attach a.:Jitional sheeis as necessar>
A.t'f r~f 5tE hw c 9-M N m er ewY
.j Cause fh* C D M e d
A eft.
l i
I f,{gy e.k fg'pgj g., h.
,h&h l
Corrective Action.
f l
l I
CATI
] Yes INo RWOA
] Yes INo Procedures Properly Follow
%Yes ] No FPOA
] Yes [No ATWSOA
] Yes TfNe PSSH Exists
- ] yes gNo Review of Similar incidents-I/M Root Cause ( Attach Part Di-I NPRDS Componeni 3 Yes g Ne NPRDS Ouen Completed ] Yes MNot Desired - NPRDS Tech or Dept. Head-Action to Prevent R-currence:
i f
CR No NCR No.
PDCR Nc.
[
Commitment No.
l Procedure Change No.
AwO No.
l Other.
Investigatot:
Date:
l 1
II. REVIEWS i
Attendees:
Management Review-Date:
Meeting No.
Date:
(PORC Reviewi 1
Comments / Action tiems l
I Follow-On Insestigation Needed.
] Yes ] No Rooi Cause Analvsis Planned 3 Yes ] No j
Presenier:
Da te:
Approved-Unit Direcior Daie:
lit. REPORT COORDIN ATOR LER No.
Date Required D.ite Sent.
Ref: ACP-Q A-10.01 SF 1001 Rev.9 Pace 3 of 4 i
4 k4
a.
PLANT INCIDENT REPORT - PART D Report No.
1 c
i A
1.
Personnel Error Eauioment Failure i
a.
Verbal communicauon a.
Inadequate design b.
Wntten communication b.
Incorrect procedure i
c.
Interface design / equipment c.
Manufactunng defect condition d.
Installation error i
d.
Environmental conditions e.
Operaung error i
e.
Work schedule f.
Improper maintenance f.
Work practices g.
Improper tesung 1.
Procedure not used.
h.
Wear out i
2.
Procedure not followed.
j.
Misoperation of another component l
3.
Verification not done.
or system 4
No self-checking h Other /xe rta se e
g.
Work organization / planning fe #3 % e.
i h.
Supervisory methods p
gg,
j i.
Training /qualificauon methods J.
Training /qualificauon content j
k.
Change management j
1.
Resource management m.
Managerial methods Ill. Proeram Failure IV.
Activity
'I a.
Procedure deficiencies:
h Surveillance 1.
Lack of detail b.
Maintenance
' 2.
Technical error c.
Equipment restorauon I
3.
Administrative error (including retest) 4.
Incomplete d.
Plant startup/ shutdown 5.
Data from wrong source e.
Safety tagging b.
Insufficient planning f.
Fire protecuon c.
Management deficiency g.
Steady state plant ops i
1.
Standards / expectations not set h.
Hot shutdown outage l
2.
Standards / expectations not i.
Cold shutdown outage monitored 3.
Inappropriate decision Investigator Signature /Date l
I Ref: ACP-OA-10.01 SF 1001 Rev.9 Pace 4 of 4 APfi 8 1991
o:
r PLANT INCIDENT REPORT - PART B PERSONNEL QUESTIONNAIRE-
[/Ald 2 bO NAME EbE C H LAC #TE4 POSITION (PRINTJ l
I EONb/d/*A/LUAG=~ If AMb PLANT EVENT TITLE EVENT DATE/ TIME 9/~//7 l
PIR Nt*MBER (IF KNOWN)
\\
$ $>t$$ve eSW WoD4, T clneso 'lkt bsd lAnnh SanN S TEST mbt llro $> N US[f8 Mh0 $ netw-lu.
WM LC $ Gm:
a ano Ja,s acci & ransGx GIEo.
kv,) a ss in E n c o euch.
>MIArbtA-)tnCC. 0 hog blt G$**b'k
- c 2.
\\\\'nen dic vou know there was a problem, and how did vou find out?
6ks[d d-id ME. Vs.o Cri%cq Lohri k deO 4,Y bing NE B R>T I sscu tt
/M us wr 1,7 a d & ne n,mos %.s
=o, L ' dKSE/,
t 3.
What Were Your actions?
?5%Cw t O YL b Ws t !, T,hb+1C D
//Ast ~'2 SS What could be done or changed to prevent this problem from happening again?
J.
n YE0Mek SclstD tD VYA 'S YM YCC' t ! MY N1MMJ AJ}f>rCE r (A
!bn.dsed&*/ pom wn,rlds
%yrd -eM t
5.
Any other information vou consider important:
$u6 > I tO tr ' O >Ht 4L TA) M9scf_ Y JhectDOA2.,
i
! erie ned i
l 1lll l9 /
I.II/.$
/14 w I
// / 4/
/ t/
' Date Time j
Supervi opiure SF 1001 Ref: ACP-O A-10.01 Rev.9 Page 2 of 4 APR 8 1931
[ ;e,
~
1; I
PLANT INCIDENT REPORT - PART B PERSONNEL QUESTIONN AIRE GCd\\ruL NAME C 56V POstTION (PRINT)
E08 d 6 FA/t.u/26' D 4 CA! b
' PLANT EVENT TITLE
/
I
/N EVENT DATETIME
~// 7 i
.PIR NUMBER (!F KNOWN) l 1.
Desenbe tne event:
gg i
1 i
2.
When di: vou know there was a problem, and how did you find out?
5
// /h OUev&\\re Conveuscde'un
&%een
~
/
cd\\
elec4Ecth h cs 4
on 3
What were your actions?
C OG Jose <vd proVm WeM
+o t
4 Aev M al cuvc) c\\ewned c esh c4 s on l
l nOS Ted e dF o
N I
What cou.: be do e or changed to prevent this problem from happtnmg again?
l J.
/
i 5.
Any other mtormauon you Consider important:
MM wn o Jefend/
h dr Q S-T\\EF)S QCO Cf')wvt o
ct 4A~TO san ocwAs cf elet4vtciW %ds sY: odd k
}
Nye) n k (905fkn%M We b yei7c,wced W!!b Sm N bite Time k
XT ture n///4/
//4'E is i
Date Time j
Supervisor Segnature SF 1001 Ref: ACP-QA-10.01 Rev. 9 Page 2 of 4
- PR 8 1991 l
C L
A INTENA NCE a.
MI 1 OF 2
.l IiMS ids M2 02 EOF EAG EMG EOFD/G WORK ORDER: M1 c1 12.O'~G
===================
I PRIORITY.....: 3 iCAL ID: EOFD/G I AWO TYPE.....:
) CAL SYS EOF I UNIT STATUS..: U MCDE: ZZ
>RDS:
3LDG: YD ROOM: EOF EUILDING I FREQUENCY....:
ILEV: 0014 FT 06 IN GRID: 2651 i SCHED START..
11 / Oo /9 1 REQ COMPL....:
<l 91
% NO:
I O. NO:
1 PROJ R E i~..... : CY11-FS-T
- .C O U N T :
- ===.=================_:==:====
JUIP DEEC: EMERGENCY OPERATIONS FACILITY DIESEL GENERATOR ASSEMBLY tOBLEM DESC:
D/G WCN'T SHIFT LOAD.
)
JSP. CAUSE:
RIGINATOR: R GAUZZA DEPT: OPS DATE: 11 / 08 / 91 TR TAG HUNG: N
{
1
+ + o w u* + w 4 % mu+ +m + m mu mu m.:5+wmmm w w.em* memon 4T-1...:
N TAGGING: N EECURITY..: N OC F EO.... ; N CONVEX....: N I
20.....:
N RWP REG: N FIRE WATCH: N HOUSEKEEP.: N FARTS LIST: N i
>GA....:
N CLEANNESS.: N TOOL LIIT.: N ISI.......-
N AEME CLASL _ _ _,
STAGIN:...: _ _, _
i
~:A..,. : N FHIELC.: ___
rqv,,; _ _.
- e '. f.LLW - N
..:. c r.
~.g.--
c,,
':C~3/623: 2 O'.'
EW-L : C D-225 UJT I Ct.i i
NOTES:
3.?
- 1) REPAI~ LGADING PROBLEM.
-E ~. C :
TASK DEPT
- WKP MAN HP TAEK DEPT
- WKP MAN HR 4.
REPAIR ELEC 5.
6.
UPERVISOR: E RGUE ASSIGN TO:
Dr.TE: [_/
' k_
EPT AFPROVAL:
PS PRE-APPROVAL:
TIME:
1.%TE :
/
iitEEEni7FAssiCATE 5 E-LCO: __ _____ DURATION: ___,___ JUMP py
____~M.---r----- t %
TIME:
4.7. o AG CLEARANCE: _
v/
DATE:
.PS APeROvAL: -
4
. +.
.s FAGE 2 OF-2
+ o c o o o c o o *
- o * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * + 4 * * +.+ * * * * + + * * * *
- m * * * * * * * * + + + + + + *
,* TAGGING VERIFIED BY:
ACTUAL WORK / PARTS:
CAUSE/ COMMENTS:
__ _________ ___ ___ ___ _ __._____.._.___.______.___.__ __________ FAIL CODE:
PERFORMED BY--
- 1 0 TE:
IER NO:
CAL DUE:
/__ /__
/-- /_
__ /_ /
/.
/
/
/
WORK COMPLETE:
COMP DATE:
/
- >*** m m + m
- m *++~ m m s.* m _*_**, m ** m
- m__m.* m__/.__
TR TAG REMOVED: N/A m m **< m e m *+ m u.*
RETEST / FUNCTIONAL VERIFICATION RETEST RESULTS METHOD / PROCEDURE RETEST #1 IAW 2701X-3.
SAT UNSAT DATA ACCEPT CRITERIA: IAW 270IX-3.
_ - - -- _ =_-
PERFORMED BY:
DEPT:
DATE:
/
/
o**o**** m
- m
- m
- m ** m *_*_m____
m * *
- m * * * + m m * *- * *
- m *
- m m m m
- m TAGS CLEARED BY:
DATE:
/
/
TIME:
ACCEPTED BY OPS:
DATE:
/
/
PMMS REVIEW:
DATE:
/
/
DEPT REVIEW:
DATE: __ / __ / __
an>.g A I N T ETN A N C,E gaa ib G
^*? AGE'1 OF 2 i
j FMMS ID:
MZ O2 EOF EAG EMG EOFD/G WORK ORDER: M2 91 12093
======r.:============
LOCAL ID: EOFD/G i PRIORITY.....: 3 i
LOCAL SYS EOF i AWO TYPE.....: CM i
NPRDS:
I UNIT STATUS..: U MODE: ZZ~
BLDG YD ROOM: EOF BUILDING l FREQUENCY....:.
[
. ELEV: 0014 FT 06 IN GRID: 2651 i SCHED START..: 11 / 06 / 91 Y j
)
-TR NO:
1 REQ COMPL....: 12 / 31 / 91
(
P.O. NO:
I ACCOUNT:
1 PROJ REF.....: CY11-FS-7
===================
EQUIP DESC: EMERGENCY OPERATIONS FACILITY DIESEL GENERATOR ASSEMBLY-PROBLEM DESC:
D/G WON'T SHIFT LOAD.
1 l-SUSP. CAUSE:
-ORIGINATOR: R GAUZZA DEPT: OPS DATE: 11 / 08 / 91 TR TAG HUNG: N
++ne******+*********+++*n*++++++++++****+++++++*******+*******************++*+
CAT-1...: N TAGGING: N SECURITY..: N QC REO....:.N CONVEX....: N EEQ.....:
N RWP REO: N FIRE WATCH: N HOUSEKEEP.: N PARTS LIST: N FPGA....: if ALARA..: N LLRT......:
N CLEANNESS.: N TOOL LIST.: N RWOA....: N SHIELD.:
ATWSOA..: U REWORK.: ___
ISI.......:
N ASME CLASS:
STAGING...:
N MOV TEST..:
ENC VOLUME: N PROCEDURES: 2701J-43 EVALsCD-228 J
CAUTION NOTES:
JOB
- 1) REPAIR LOADING PROBLEM.
DESC:
TASK DEPT
- WKR MAN HR.
TASK DEPT
- WKR MAN HR h
1.
REPAIR ELEC
_/_ _ _ _
_d._G _
4.
=. gg m. s e.
3.
'Y-6.
SUPERVISOR: B ROWE ASSIGN.TO:
DATE: [_ /
/
DEPT APPROVAL:
- no******* m ***** m ***** m m *** m m
- m ****** m ****** m ****** m m m OPS PRE-APPROVAL:
TIME:
DATE:
/ __
TRBLSHT/ FABRICATE ONLY TAG CLEARANCE: _
LCO:
_,__ DURATION:
_ JUMPER:
_h/ Y
_ _ _ _ _'L TIME: __h_h__
OPS APPROVAL:
DATE:
p'
WORK ORDER: M2 91 12.093 f.
(
l-
.j.. PAGE 2 OF 2
. eco***** n*******************n
- * * *
- n
- n * * * * *. * *
- m m m *
- n n * * * *
- m w
- n TAGGING VERIFIED BY: -- ----- _/J.J_ - - -- - - ----
ACTUAL WORK / PART,S: _._ _ - _ - - _ _ _ - _ _ _ _ _ M. _ _ M
-____.__________4_
_----------------_c o A '.
tsu-f A
5e6-ll f(
~
__/-
=-----------------
CAUSE/ COMMENTS:
e FAIL CODE:
4M M
/
- ------_. E___4.5__-
PERFORMED BY:
- - M ----..
M & TE:
/
/
/
/
/
/
/
/
/
/'
/
/
f WORK COMPLETE:
COMP DATE:
TR TAG REMOVED: N/A
- * *
- w * <- * * * * *
- n + * * * * * * +. *
- n
- m *-
- m
- n
- n * * * > n u m
- RETEST / FUNCTIONAL VERIFICATION RETEST RESULTS METHOD /FROCEDURE O[-~
-SAT UNSAT RETEST tti IAW OTO1X-3.
DATA Wd '.L 8.TtAS$-t
-_----------=
l ACCEPT CRITERIA: IAW 2701X-3.
==-_ <
l Nh DATE: M/
/
DEPT:
PERFORMED BY: __********** m *********u*****dn*C
- m **** n *************
.o*********n**
)
- - - ~ ~ ~. - - -
\\
TAGS CLEARED BY:
DATE:
/
/
TIME:
~
=-----
ACCEPTED BY OPS:
DA.TE: / 3. / f' /
_I_D7 h / h -
DATE:
FMMS REVIEW:
DATE: /f f G
-_/
DEPT REVIEW:
T i
e EMERGENCY OPERAh0N FACD lTY EMERGENCY DIEM.L GENERATOR V
OPERABLLITY TEST SURVEILLANCE COVER SHEET onts Pact
- r. f } (A t4 -
N D bl (I
ocx ox:<c.?,0
/ rd*.s t i
OF 1 1
- /
/
)
serenewce sate.
~
J
'REFERENCi PROCEoVRE SoMC MTO. No. N I ~ D l
NA EPIP 4606 SCP13ULE oart,
APPLecASLE Moot FREoutNCY j
All W
1 TEST AUT>ecei2EgBY oATE ACCEPTANCE CRITERIA MET:
a.
l M - f-9 /
- e b')
A iss,scoi
~
- 12-M/
- N1 i
y_
O oAh Acc m
)
j
,fp gg, APPaovgo sv toEPAmmENT MEW oATE NO I
MAINTENANCE SYSTEM NON-TECH SPEC O TECH SPEC ISI TESTING I
SURVEILL.ANCE RESTORATION AllONMENT SURVE!LLANCE i
TEST EQUIPMENT OA NUMBER CAL OUE C ATE i
-l ACCEPTANCE CRITERIA J. With the Transfer Control Test Panel selector Switch in the "WITH LOAD" position, and the Test Transfer Switch pinced in the
- TEST" position, the Emergency Operations Facility Emergency Diese!.
O nernent shoii d,nerfntm as follows' I
l 1.1 Start automatica!!y i
1.2 Pick up the load j
- 1..t Run for one hour INITIALS 8N SCCCPP ANec v'lTH AEFERENCE PROCEDURE 9.
PRE *EQU1!iTESMNITIAL CONDITIONS COMPLETED (M
M E'--
2.
PAFCA0TIONS NOTED
, CC YMEN'S (
- PA AINTENANCE RESTORATION. INDICATE BELOW WORK ORDER s. ETC.)
i Note: Forward completed data sheet to Station Emergency Coordinator.
Forward comoleted may of data sheet to Operations Technician i
n.lcris
- n. _
WC
- . t.;.: nour : ;r::::ity run complete I
nitials) 2.* Diesel Fuel Storage Tank Level
/
l EPLP FORM 4606-1 Rev.3
~-
..- ~..
+ '
e
"('
/- f ' M '
Y jf,h Q.,
uncuvt o^n
!/*/ 91 i
mc um 90.
- :ons 4p6vco sv t;Nd 2 0:ncF>a J
MISCELLANEOUS EQUIPMENT RLTEST MKITlIX
- 4 *
- 3
- 1
~
- 2 Perform routine Perform General Monitor component Record component Amperage and Operational Cheeks Leak Test. Monitor Vibr3Gon.
(if componentis ensure value is - to and en:ure ani component for no '
included in Unit's or less than 1.1x
~~'
operabil!!y require. leakage at Vibration Program) name-plate value.
mechanical joints.
Incars are met, i
ACCUMULATORS X
AIR-CIRCUlT BREAKER N
E
- AtR-CONDTt10NINO i
N N
AUXILIARY BOILER X
BACK FLOW PREVERTER X
EAratRIES,
j X
mREAxERs X
CHAROER X
X X
canuRs Maint Form 2701X-3 Rev.O Page 1 of 4 Q
st '
61 a1 as Perform routine 1%rform General E -Ow e ------:+- - Record e-i-:=-e l
Operstloont Checks IAnkTest Monitor Tibranca.
Ampenge and t
.na ensure any e form of e is eas== value is - to included in unies or sess than 2.2x y
operahnin rmania-leakase at
,ncias,,,, ec;
.=s= =2,%
vier.so, ytogr.m) a ysy v.i.e.
X.!
X X,,
X i
i cOMrRr.ssORs i
CRANE OR HOlsT X
DAMPER X
X DEMINERALII.ER
\\
E DIESEL GENERATOR X
EXPANs10N JOINT X
X X
rAN j
norEa
'X X
1
[
FIRE PROTICTION Maint Form 2701X-3 i
Rev. O Page 2 of 4
,ia a
m
- (f
'ys
~
PIR INVESTIGATION NOT REPORTABLE t
TO:
Brendan J. Duffv FROM:
Unit 2 PIR Report Coordinator (Tel. x4423) i You have been assigned as investigator for PIR 91-123. dated 11/8/91.
This PIR has been initially' assessed to be not reportable under 10CFR50.73.
i To support the PIR adminstrative routing process, a timely response is imperative. The PIR investigation is to be completed by 02/16/92.
INSTRUCTIONS FOR PIR INVESTIGATORS 1.
Per ACP-QA-10.01,6.2.4, the assigned Investigator shall Complete Section 3 of'the PIR.
a.
b.
Verify (if applicable) the use of emergency operating procedures and document their review and use.-
2.
Ensure that if a PIR is generated due to a failure of any RPS/ESF channel-l on a quarterly test program, that an evaluation for a common cause mode -
will be performed under the ICR program IC 2437A.
3.
Section Ill of the PIR must be filled out in its entirety. All PIRs that require PORC approval must be reviewed by the appropriate department head
. prior to PORC presentation.
4.
Particular attention should be payed to identifying correctly the root cause of the event. The root cause may be defined as "the cause which, had it been prevented, would have prevented the event."
)
NOTE: If, during the course of your investigaiton, you determine that this event may be reportable, notify the Unit 2 Operations Manager or i
Duty Officer.
)
5.
Forward the completed PIR investigation to the report coordinator.
l cc:
LER Coordinator. S. E. Scace. R. J. Factora. S. M. Temole
/
th}t rer 'i l'tu f. -
\\t ' HN 0NY l
s FORM APPROfED BY OlRECTOR, MILLSTONE STATION EFFECTIVE DATE SORC MTG NO.
PLANT INCIDENT REPORT - PART A Report No.: 2 - 9_/_
_L J_.1 INITIATION Unit Year Number To be completed by I.
PIR INITI ATION (Responsible Supervisor) INCIDENT DATE:ff.p.g, INCIDENT TIME:
REPORT DATE:re.c9, Evrnt
Title:
/.~, a r*
D,.ru4 beta rr a.Tef
[4
- 4. Jr 7'i '
/M6 Drscription of Event: Ab J' h:1 ie t Ondworr%r
[A. L. A s'D L'A J.ai maer"~st.eie.,
%.u L e it.)<a t.e,m
./i/2 /2 1/f o 6 r
^^
Deteriotioc of Suspected Cause: (if Known)
Personnel Questionnaires Attached: (Part B) Q Yes Q No System Affected:
System Number:
PMMS ID bumber:
Signature:
Date:
11.
PLANT INFORM ATION (To be completed by SS)
Plant Conditions:
Mode:
Power (%):
Temp.
Pressure:
_ cy 3
g gy D2scripticr: of initial Action:
/) If. M /~f g4
/J1/J ew /~gfy,Cprit,c Sstets Imotications:
Eff fif) cit up
/ksJan A5*f
/)ds4*l.rJ/1LIC Security implications:
/t 'c'sA.
Incident Category:
Basis (Not Required for D)
Q A. Immediate Q B. 30-Day LER Q C. Public Interest gfj g9
,y
_. y
@D. Not reportable to NRC O E. Fitness for Duty I
Operations Manager boufted (Normal Houro of A.B.C Incidents.
@ Yes O No Name: 7 ff>f,j //
Date: p.f -9/ Time: //,co l
Duty Officer Notified:
@ Yes Q No Name: 7 g,g Gp.J Date: /f.j..ff Time: /4 V6 1
I i
SSSA Notified and EPIP 4112 Notifications Made:
O Y>s @No Name:
e.
3 Date:
ft, f 3 Time:
,t, i a
e 1 l Sicurity Shift Supervisor (Potential Security Threat): Q Yes Q No Name:
, t,, ;
Date:
f ar s '
Time:
<*e/
Snitt Supervisor Signa c:
Date:
Procedures Used:(t*r/*
'l i s' l 10 Ld it - t * */ '
!!!. Dt.,TY OFFICER REVIEW Rrportabilltv Verified M Yes Q No j#,
immediate Investigatioti' Required Q Yes No l Investigator Assigned:
M (Provide Copy of Part A SF 10011 (Required for Emergencv Plan
'- sti67. Uisplinned RPSIESF Actuation. Reportable Oi/ Chemical Spill. Serious Iniurv'Fatalitv1 Duty Offim Signature:
dr,=' h o Date: /r/AP/9/
IV.
UNIT DIR ECTOR REVIE'W O
//
Reportat;ility Verified:
gYes Q No SORC Review:
O Yes S No (Required for RPS/ESF Actuation) l PORC Review:
Q Ye/ @ No (Required for Tech Spec violations, reportable events. PSSH) j PSSH:
O Yes ;Tg No NRB Review: Oyes 3 No NEO 2.25 Initiated:
O Yes 2 No.
y j
g Investig.* tor Assigned:
g Unit Director Signatu ate:
V.
INVESTIGATION INFORMA M (To be completed by Investigator)
/)
/'
Trouble Reports Submitted:
O Yes O No PrWcedure Changes:
Photographs: 0 Yes @ No Material Bemg Held:
O Yes @ No Location:
AWO Copy Attached:
O Yes 3 No Safety Tag Sheet Copv Attached: ] Yes Q No
~
Investigator Signature:
Date:
Ref: ACP-QA-10.01 SF 1001 Rev.10 t
Page 1 of 5 l
1
PLANT INCIDENT REPORT - PART C Report No.
PHASE I INVESTIG ATION Kimilar PIRs (Within last 12 months) List or attach hst.
Onen PM/ cms List or attach list.
t Recent Work Historv- (Within last 6 months) List or attach list.
Pentline Desien Channest List or attach list.
4 a
l Other Pertinent Infnrmatlan?
1 4
l Trends Identified: O Yes Q No I
i Phase II Investiention Comolete O Yes Q No 1
If NO expected compleuon date
/
/
(Not to exceed 3 months)
~
~
I Manneement Review: (R'equired within a few working days)
Date:
/
/
Investigator Signature:
Date:
/
/
I Ref: ACP-OA-10.01 SF 1001 Rev.10 Page of f f.'C V 4 1991
1
\\
j.
PLANT INCIDENT REPORT - PART_E Report No.
ROOT CAUSE Select at least one major and one minor root cause category. (Circle applicable items) '
1.
Personnel Error II.
Enuloment Fallure I
a.
Verbal communication a.
Inadequate design b.
Written communication b.
.ncorrect procedure c.
Interface design / equipment c.
Manufacturing defect condition d.
Installation error d.
Environmental conditions e.
Operating error e.
Work schedule f.
Improper maintenance f.
Work practices g.
Improper testing 1.
Procedure not used-h.
Wear out 2.
Procedure not followed.
j.
Misoperation of another component 3.
Verification not done.
or system 4.
No self-checking k.
Other g.
Work organization / planning h.
Supervisory methods 1.
Training / qualification methods j.
Training / qualification content k.
Change management 1.
Resource management m.
Managerial methods III. Proeram Failure a.
Procedure deficiencies:
1.
Lack of detail 2.
Technical error 3.
Administrative error 4.
Incomplete 5.
Data from wrong source b.
Insufficient planning c.
Management deficiency 1.
Standards / expectations not set 2.
Standards / expectations not monitored 3.
Inappropriate decision 1
l i
i Ref: ACP-QA-10.01 SF 1001 Rev.10 Page 5 of 5 IICV i391 m
N PLBbfC DISCAOSW issue 91-219-01 Cheges to vendor maintenance and surveillance instructions are not evaluated and needed procedure changes are not being made in a timely manner. In particular, MP 2720R 1, NAMCO Limit Switch Maintenance (EQ), references NAMCO EA 189-90051 (Decembe",1980) whereas the vendor has superseded EA 189-90051 with EA 189-90060 (February 4,1991). This new information warns that removal of the bottom cover of the limit switch will negate the qualification (EEQ). In addition, NU was notified in May,1989 that the vendor would no longer support re-work and spare part hits for their solenoid valves and limit switches. The concern is that key craft personnel are not aware of these changes.
Issue 91-219-02 MP 2722B, Annual EOF Diesel Generator Load Run, is deficient in that the division of work responsibilities among electricians, mechanics, and contractors have never been evaluated as appropriate. Further, AWO M2-89-09594, for the annual load test, does not reference MP 2722B or the other controlling procedure, EPIP 4303, and, there appears to be the following discrepancies in the drawings associated with the test:
1)
Electrical circuit breaker positions on electrical panels KLP1 and KLP2 do not agree with drawing 25205-30007. Circuit breaker No. 26 is in question on ELP1; breakers 10 and 12 are in question on ELP2; 2)
An electrical remote control panel, PNI is shown on drawing 25205-30007; but does not appear to exist; 3)
The schematic portion of drawing 25205 39002, sheet 3 (or 25205-32008) appears incorrect and is confusing; 4)
A utility plug is located at the bottom of the electrical power distribution system automatic bus transfer device (ABT). This conflicts with drawing 25205-32008; 5)
The vendor representative and mesanic involved with the antalload test of the EOF emergency diesel generator are not qualified to perform the electrical portions of the test; and, 6)
The review of procedures made by PORC is inadequate.
Request:
Please discuss the validity of the above assertions. If any deficiencies are identified, please provide us with the corrective actions you have taken to prevent recurrence.
Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.
W 15CLG5URE
W f
)
h j-
.[ ***%
UNITED STATES l
9p, NUCLEAR REGULATORY COMMISSION
/
['
fh e
h f
MEG 8oN I 475 ALLENDALE ROAD KING OF PRUSSIA. PENNSYLVANIA 19406-1415
'g **"*
MOV 0 61991 Docket Number: 50-336 Northeast Nuclear Energy Company ATrN:
Mr. John F. Opeka Executive Vice President - Nuclear Engineering and Operations Group 1
P.O. Box 270 l
Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
i Thank you for informing us of the results of your reviews of the concerns 'isted in the enclosed table. We have performed verification inspections on selected issues, find your responses generally acceptable, and plan no further actions on these issues at this time. This is not to say l
that further independent reviews of these issues will not take place in the future. You will be l
kept informed of such verification inspections and independent reviews by the normal inspection l
report process.
A ccpy of this letter as well as the referenced correspondence is being placed in the Public Document Rooms and sent to the State of Connecticut. We appreciate your cooperation in these
.2.
3..o J ',
g j
P' Edward Wenzinger, Chi,efj f Reactor Projects 'BranchW l
A
Enclosure:
Table of NU's Responses l
\\
cc wiencl:
Public Document Room (PDR)
Local Public Document Room (LPDR)
State of Connecticut
)
NORTHEAST UTILmES c.n.,.i ome... s.ma si
. a.mn. cona.ci.cui ARTF0AD. CONNECTICUT 06141 o270 L
L TJ 7,:ll:'d,'O.L***.'."
(203) 665 5000 September 30, 1991 Docket No. 50-336 A09829 Mr. Charles W. Hehl, Director Division of Reactor Projects U.S. Nuclear Regulatory Comission Region I 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Hehl:
Millstone Nuclear Power Station, Unit No. 2 RI-91-A-0210 We have completed our review of an identified issue concerning activities at Millstone Station. As requested in your transmittal letter, our response does not contain any personal privacy, proprietary, or safeguards information.
The material contained in this response may be released to the public and placed in the NRC Public Document Room at your discretion.
The NRC transmittal letter and our response have received controlled and limited distribution on a "need-to-know" basis during the preparation of this response.
LSSUE 210-1:
" Millstone 2 turbine sampling system valves with a prefix of '0-S' are not labeled in the field.
In addition, the so.~um analyzer 'AE 7764 A5', is incorrectly labeled as 'AE 7764 A6' on sheet 3 of drawing 25203-26025."
RE00EST:
"Please discuss the validity of the above assertion.
If the above conditions are valid, please notify us why this was not previously corrected by your j
labeling program and what corrective actions you have taken to prevent recur-
)
rence.
Please provide us with an assessment of the safety significance of any identified deficiencies, including any generic considerations.'
RESPONSE 210-1:
The assertion concerning the sampling system valve labels is valid if the stated analyzer is AE7784 rather than AE 7764. We were made aware of the drawing problem in early September, 1991.
The Millstone Unit No. 2 Engineering Department has identified that the Piping and Instrument Diagram (P&lD) does not agree with the as-built condition and is in the process of updating the drawings to reflect the as-built conditions.
j O)
@ & flf
I i
?
Mr. Charles W. Hehl A09829/Page 2 September 30, 1991 In March 1991, a new Administrative Control Procedure, ACP-6.22--System and Component Labeling-was written and issued to provide guidance on a standard-ized labeling program for the Millstone site.
Also in March, a Controlled Routing (CR 8139) was issued to track the progress of each of the units in complying with the requirements of the ACP.
The labeling effort includes i
valves, majorcomponents, and instrument and gauge labeling. The sampling The valve system yglves identified in the assertion are part of this program.
labeling efforts are expected to be completed by the end of 1992. Currently
~~
the Operations Department is holding discussions with other departments in the unit in an effort to establish who will normally operate and be responsible for labeling valves such as those associated with radiation monitors, sample systems, etc.
As part of the program implemented under ACP 6.22 a label request form has been generated which allows anyone finding a missing, incorrect, or deterio-rating label to bring it to the attention of the label coordinator or Opera-tions Manager for prompt action.
As part of the labeling program under ACP-6.22, the initial labeling of a system is to be verified by a complete walkdown of the system using system checklists and P&lDs to determine that all system components are labeled and that the label nomenclature matches the P&lD identification and system check-list description for each component.
Thus, if other similar problems exist, they should be routinely identified and corrected as part of this program.
ISSUE 210-2:
" Circuit changes had been made to the Millstone 2 main generator hydrogen monitor without the preparation of a modification package. As a result, the calibration procedure is inadequate, and appropriate procedure and drawing changes have not made."
RE0 VEST:
"Please discuss the validity of the above assertion. If the above conditions
(
are valid, please notify us of the corrective actions you have taken to i
prevent recurrence.
Please provide us with an assessment of the safety signi-ficance of any identified deficiencies, including any generic considerations."
RESPONSE
We are still investigating this matter and will respond when the investigation is complete. We currently plan to respond by October 14, 1991.
Mr. Charles W. Hehl A09829/Page 3 September 30, 1991 After our review and evaluation of this issue, we find that it did not present any indication of a compromise of nuclear safety. We appreciate the opportu-nity to respond and explain the basis of our actions. Please contact my staff if there are further questions on any of these matters.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Edwaff J. MrocWfk Senitr Vice President cc:
W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 E.
C.
Wenzinger, Chief Projects Branch No.
4, Division of Reactor Projects E. M. Kelly, Chief, Reactor Projects Section 4A J. T. Shediosky, U.S. Nuclear Regulatory Comission, Millstone
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k UNITEo STATES NUCLEAR REOULATCOY CSMMISSION
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e 3 475 ALLENDALE RoAo KING oF PRUSSIA. PENNSYLVANIA 19406-1415 "g
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50-336 0CT 0 91991 File Number:
RI-91-A-219 Northeast Nuclear Energy Company ATTN:
Mr. John F. Opeka Executive Vice President - Nuclear Engineering,and Operations Group Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
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 Gle number *0lename* 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 concem has been completed and reviewed by NRC Region 1. 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 Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation in this matter will be appreciated. We will gladly discuss any questions you
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have concerning this information.
Sincerely, Y
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Cha s W.
1, Dire <: tor Division of Reactor Projects
Enclosure:
10 CFR 2.790(a)Information Issues and Requests W 4 Cubs fY
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I Public Document Room (PDR) local Public Document Room (LPDR)
State of Connecticut I
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mm ess sooo November 15, 1991 Docket No. 50-245 B13963 Re:
RG 1.97 Inspection 50-245/91-20 U.S. Nuclear Regulatory Comission 7
Attention: Document Control Desk Washington, DC 20555 i
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 Reaulatory Guide 1.97. Revision 2 (TAC No. 51106)
An inspection of Millstone Unit No. I compliance with the provisions of Regulatory Guide (RG) 1.97, Revision 2, was conducted by the NRC Staff from response to the Staff's Safety Evaluation,g In Northeast Nuclear Energy Compan September 30, 1990, toOctog4,1991.
(NNECO) September 11, 1991, NNECO comitted to provide the Staff with pertinent changes regarding addi-tional Type A variables by the end of the year.
During Inspection 91-20 NNECO made a more specific comitment to provide the status of its review by J
November 15, 1991.
The purpose of this letter is to satisfy that comitment.
The following RG 1.97 variables are now considered to be additional Type A variables for Millstone Unit No.1.
Torus bottom pressure Drywell temperature Low-pressure coolant injection (LPCI) flow Core spray flow Emergency service water (ESW) to LPCI differential pressure (1)
E. J. Mroczka letter to U.S. Nuclear Regulatory Comission, "Conformance to Regulatory Guide 1.97, Revision 2 (TAC No. 51106),"
dated September 11, 1991.
(2)
N. L. Boyle letter to E. J. Nroczka,
" Millstone Unit 1--Request for l
Additional Information Regarding Conformance to Regulatory Guide 1.97, Revision 2 (TAC No. 51106)," dated April 24, 1991.. -
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U.S. Nuclear Regulatory Comission B13963/Page 2 November 15, 1991 The first two of these five variables, torus bottom pressure and drywell temperature, completely satisfy the provisions of RG 1.97 for Type A vari-ables.
The other three variable's, LPCI flow, core spray flow, and ESW to LPCI differ-ential pressure, have areas where deviations from the provisions of RG 1.97 will be taken by NNECO. Details of these deviations are provided below.
LPCI flow:
RG 1.97 specifies redundant flow measurement loops.
Millstone Unit No. I has one flow measurement loop in the selected path (by the loop selection logic) for LPCI injection into the reactor pres-sure vessel.
Also, the measurement loops are powered by the instrument AC Circuit Breaker No. 45, while the RG calls for redundant power sup-plies.
Core spray flow and ESW to LPCI differential pressure are not recorded as recommended by the RG. Also, these variables do not have redundant power supplies as recomended by the RG.
An evaluation, which was performed as part of preparations for start-up from the 1991 refueling outage, concluded that the instrument redundancy and power source deviations described above do not detract from the safe operation of Millstone Unit No.1.
Lack of recording of core spray flow and ESW to LPCI differential pressure as recommended by RG 1.97 also does not detract from the safe operation of Millstone Unit No.1.
NNECO plans to finalize a course of action to address the deviations for the variables discussed here by the end of March 1992.
Please contact us if you have any questions.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY td J.F(OpJka (J
ExecutTve Vice President cc:
T. T. Martin, Region I Administrator D. H. Jaffe NRC Project Manager, Millstone Unit No. I W. J. Raymond, Senior Resident Inspector, Nillstone Unit Nos.1, 2, and 3
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UNITEo STATES
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e 475 ALLENoALE RoAo KING of PRUSSIA. PENNs'tLVANIA 19406-1415 NOV 2 6 891 Docket No. 50-245 Mr. John F. Opeka Executive Vice President - Nuclear Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
Subject:
Inspection Report No. 50-245/91-20 The report is enclosed of the inspection conducted by Mr. R. Paolino of this office on September 30 through October 4,1991, of safe shutdown equipment, Regulatory Guide 1.97, at Millstone, Unit 1 in Waterford, Connecticut. These activities are authorized by NRC Operating License No. DPR-21. Discussions of the inspection findings were held by Mr. Paolino with Mr. L. Davison and other members of your staff at the conclusion of the inspection.
Specific areas examined during the inspection included your compliance with the orders issued to implement Regulatory Guide 1.97.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Based on this inspection, it was determined that the post-accident monitoring program implemented by your staff is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, with the following exception. One unresolved item, involving missing environmental qualified (EQ) components from the current EQ master list, Revision 4, was observed. We note that the draft, Revision 5, of the EQ master list, includes the missing EQ components.
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In discussions with instrumentation and control engineering personnel, it was indicated that a comprehensive review was in process regarding the status of five probable additional type A variables. We understand that final resolution of this review is scheduled for November 15, 1991, at which time the NRC would be notified.
Within the scope of this insp ction no violations were identified.
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No reply to this letter is required. Your cooperation with us in this matter is appreciated.
Sincerely, n
nn ma Jacke P. Durr, Chief Engineering Branch Division of Reactor Safety
Enclosure:
NRC Region I Inspection Report No. 50-245/91-20 cc w/ enc 1:
W. D. Romberg, Vice President, Nuclear Operations S. E. Scace, Nuclear Station Director H. F. Haynes, Nuclear Unit Director R. M. Kacich, Manager, Nuclear Licensing D. O. Nordquist, Director of Quality Services Gerald Garfield, Esquire Nicholas Reynolds. Esquire K. Abraham, PAD (2) All Inspection Reports Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Connecticut bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
J. Joyner, DRSS E. Kelly, DRP E. Wenzinger, DRP W. Raymond, SRI, Millstone A. Asars, SRI, Haddam Neck R. Lobel, EDO D. Jaffe, PM, NRR DRS SALP Coordinator DRSS SALP Cordinator R. Arrighi, DRP 1
U. S. NUCLEAR REGULATORY COMMISSION REGION I Report No.
50-245/91-20 Docket No. 50-245 License No.
DPR-21 Licensee: Northeast Nuclear Energy Company
"' P.O. Box 270 Hartford, Connecticut 06140-0270 Facility Name: Millstone Nuclear Power Station, Unit 1 i
Inspection At: Berlin, Connecticut Inspection Conducted: September 30, 1991 - October 4,1991 tw b
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Inspectors:
R.JJ. Paolino,'Sr. Reactor Engineer, date Electrical Section, EB, DRS Other Participant and Contributor to this Report i
Alan Ud, on Lu ant, EG&G Idaho, Inc.
Approved by:
// / 6 N C. y Anderson, Chief. Electrical Section,
' date Engineering Branch, DRS Inspection Summary Areas Inspected: Special announced inspection to review the licensee's implementation of the post-accident monitoring instrumentation in accordance with Regulatory Guide 1.97, Revision 2.
Results: Based on this inspection, the inspectors determined that the licensee has a program that meets the recommendations of Regulatory
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Guide 1.97, Revision 2, with the following exceptions.
The licensee's 3
current EQ Mastar List, Revision 4. did not list all of the EQ components located in a harsh anvirer. ment..
This was identified by the licensee who 1
was in the process of issuing a revised EQ Master List, Revision 5, that included the missing components.
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DETAILS 1.0 Introduction
Background
The purpose of this* inspection was to verify the implementation of
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Regulatory Guide 1.97, Revision 2, for instrument systems used to assess plant conditions during and following an accident. These systems were inspected to determine if they were installed in accordance with the 1
requirements of Generic Letter 82-33, " Requirements for Emergency Response Capability" (Supplement No. I to NUREG-0737). This letter,.
issued on December 17, 1982, specifies those requirements for emergency response capabilities approved by the NRC for implementation. This supplement also discusses, in part, the application of Regulatory Guide.
I 1.97 to the emergency response facilities, including the control room, the technical support center (TSC), and the emergency response facility (EOF) at nuclear power plants.
Regulatory Guide 1.97 identifies the plant variables to be measured and the instrumentation criteria for assuring acceptable emergency response capabilities during and following an accident.
1 Regulatory Guide 1.97 divides post-accident instrumentation into three categories and five types. The three design categories are Categories 1, 2, and 3.
Category 1 has the most stringent design requirements and Category 3 the least stringent.
The five types of instrumentation identified in Regulatory Guide 1.97 are Types A, B, C, D, and E.
Type A variables are plant specific and classified as such by the licensee. Type B variables indicate the accomplishment of plant safety functions. Type C variables provide information on the breach of barriers to fission product j
release. Type D variables evidence the operation of individual safety I
systems. Type E variables are those used to determine the magnitude of the release of radioactive materials.
Each variable is assigned to a design category by the regulatory guide. However, Type A variables can only be design Category 1.
,j Correspondence The licensee responded to Regulatory Guide 1.97 for Unit 1 in submittals dated April 9, 1984, October 25, 1985, November 25, 1985, and July 31, 1986.
These submittals address conformance to Regulatory Guide 1.97, Revision 2, along with supporting justification or alternatives.
3 References The specific references used to assess the licensee's response to Regulatory Guide 1.97 are identified below:
Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-water-cooled N0 clear Power Plants to Assess Plant and Environs Conditions During and Following Accident."
Millstone-1 Safety Evaluation Report - Conformance to Regulatory Guide 1.97, April 24, 1991.
Supplement No. I to NUREG-0737, " Requirements for Emergency Response Capability (Generic Letter No. 82-33), " December 17, 1982.
Inspection Scope The NRC inspection scope included: equipment qualification (setsmic and environmental), redundancy of power sources, measured variables, display and recording methods used, independence and separation of electrical circuits, range and overlapping features of multiple range instruments, equipment identification for Regulatory Guide 1.97 instruments, service, test, and surveillance frequency, and direct versus indirect measurements of parameters of interest. The plant maintenance and monitoring system (PMMS) printout and the EQ master list were reviewed for the instruments selected to ascertain whether the instruments had been evaluated and tested to the appropriate environmental and seismic qualification requirements.
The inspectors also reviewed the QA procurement of these instruments.
2.0 Inspection Details The inspectors held discussions with various members of the licensee's staff, reviewed drawings, procedures, and plant lists for selected variables. The inspectors performed a walkdown of the control room instruments to assess the implementation of Regulatory Guide 1.97, Revision 2, for Millstone 1.
The inspectors found all instrument loops in calibration. Calibration records show that calibration and surveillance is performed at the specified frequencies.
The licensee has green borders on the right and left sides of the instrument tags for the primary readout device. Thus, where a variable has both indicator and recorder on the same instrument loop, only the preferred readout is marked in this manner. The inspectors found this acceptable. The inspectors also noted that calibration stickers have a vertical green band on them. This preponderance of vertical green borders could be potentially confusing to the operator in finding the instruments associated with the regulatory guide. However, the inspectors found no basis for finding this condition unacceptable, as the calibration stickers are distinguishable from the instrument tag labels.
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j The inspectors reviewed design, operational, and surveillance details for i
I the following variables.
Reactor pressure vessel pressure, Type A, B, and C, Category 1 Reactor pressure vessel water level, Type.A and B, Category 1 Torus water temperature, Type A and D, Category 1 Torus water level, Type A, C, and D, Category 1 Drywell pressure, Type A, B, and C, Category 1 Neutron flux, Type B, Category 1 Drywe11 area radiation level - high range, LType E, Category 1 Containment isolation valve position, Type B, Category 1
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Characteristics examined for each variable include identity. location, function, separation (electrical and physical), isolation, power sources, environmental qualification, seismic qualification, and instrument range.
The items examined for compliance with Regulatory Guide 1.97,- Revision 2, are discussed in the remainder of this report.
2.1 Reactor Pressure Vessel Pressure The licensee determined this variable is a Type A variable.
Two redundant instrument channels, each powered by a separate DC-power t
source, indicate this vari'able with a range of zero to 1500 psig.
Two other channels provide the recording function on a single recorder.
The signal is recorded for either of these two loops, dependent on the position of a selector switch. The selected signal is also recorded by the plant computer. The signal is isolated as recommended by the regulatory guide. These channels, with a range of zero to 2500 psig, have an instrument AC power source. Considering these channels as a single recording channel with two additional independent Category 1 channels, the Category 1 requirements have been met.
No deficiencies were identified.
2.2 Reactor Pressure Vessel Water Level The licensee determined this variable is a Type A variable.
Two redundant instrument channels, each powered by a separate instrument AC power source, indicate this variable with a range from -340 i
inches to a +60 inches. Both channels are recorded by the plant computer. The signals to the plant recorder are isolated from the instrument loops as recommended by the regulatory guide.
The inspectors verified conformance with the Category I requirements.
No deficiencies were identified.
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5 2.3 Torus Water Temperature The licensee determined the torus water temperature is a Type A variable. The licensee monitors the torus water temperature with 26 resistance temperature detectors (RTDs) distributed throughout the l
torus.
Four of these RTDs are divided into two channels of instrumentatidn, Each channel has a separate instrument AC power source and is indicated on a dual indicator. These four signals are also recorded by the plant computer which are isolated from the
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instrument channels.
The other 22 RTDs are recorded on two multipoint recorders, each with a separate. instrument AC power supply, eleven RTDs per recorder. The inspectors determined this variable to be in conformance with Category I requirements.
The inspectors noted that the indicators and their computer inputs have a range of zero to 300*F, while the licensee's submittals show a range of 30'F to 300'F.
The multipoint recorders have scales of 30'F to 230*F.
Regulatory Guide 1.97 recommends a range of 30*F to 230*F and, therefore, all indication of the torus water temperature meet or exceed the regulatory guide recommendation. Therefore, the inspectors concluded that this instrumentation is acceptable.
2.4 Torus Water Level The licensee determined the torus water level is a Type A variable.
The licensee has two instrument channels for this variable with a range of 2.2 feet to 27.2 feet.
Each channel is displayed on a dual pen recorder shared with the variable drywell pressure and is also recorded by the plant computer. The computer inputs are isolated from the instrument channels.
Each channel is powered by a separate instrument AC power source.
The inspectors determined the Category I requirements have been met.
No deficiencies were identified.
2.5 Drywell Pressure The licensee determined the drywell pressure is a Type A variable.
The licensee has two instrument channels for this variable with a range of -5 psig to +250 psig. Each channel is displayed on a dual pen recorder shared with the variable torus water level. Each channel is powered by a separate instrument AC power source.
The inspectors determined the Category I requirements have been met. No deficiencies were identified.
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.6' 2.6L Neutron Flux The. Regulatory Guide 1.97 classifies neutron flux monitoring as a Type B,. Category 1. variable.. The neutron flux instrumentation channels are powered by redundant electrical buses which are backed up by the
.I gas turbine or the diesel generator.
Two source range. monitor (SRM) channels and* four intermediate range monitor (IRM) channels receive
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power from a DC power source. Two other independent' SRM channels and four additional independent IRM channels receive power from a second.
DC power source. The six average power range monitor (APRM): channels receive power from reactor protection system 120-Vac buses, three channels per bus. Environmental and seismic qualification were not in evidence, though.some components are in a mild post-accident.
environment.
The licensee is part of the Boiling Water Reactor Owners Group (BWROG) and part of the appeal on neutron flux instrumentation Category I requirements. The resolution of the BWROG appeal is pending.
In the meantime, interim operation with the SRM, IRM, and.
APRM channels is acceptable per the safety Evaluation Report.
2.7 Drywell Area Radiation - High Range Regulatory Guide 1.97 classifies this as a Category 'l variable. Two' channels, each powered by separate instrument AC power sources, monitor from 1 R/hr to 10' R/hr.
Each channel has an indicator and 2
one channel is also recorded by a dedicated strip chart recorder.
l The inspectors determined the Category I requirements have been met.
No deficiencies were identified.
2.8 Containment Isolation Valve Position Regulatory Guide 1.97 classified containment isolation valve position as a Category 1 variable. The inspectors audited material related to i
the position indication of the containment isolation valves. High reliability is. achieved in containment isolation valve's position '
indication by a combination of redundancy and diversity of power J
sources. Power for a typical pair of valves consists of 480V AC bus power to one motor-operated valve motor and indication and 125 volt DC bus power for the corresponding DC motor-operated valve motor and
-l indication.
The inspectors determined the Category 1 requirements have been met.
No deficiencies were identified.
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t 2.9 _ Isolation Devices Where a Category 1 signal inputs a 'non-category 1 system, Regulatory Guide 1.97 specifies the use of isolation devices that are qualified
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for use in Category 1 circuits. Circuits examined during this.
inspection have proper isolation. The separation criteria was implemented appropriately.
Instrument loops that interface with
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computer circuits have appropriate' isolation amplifiers. Circuits that feed annunciators use relay contacts for isolation.
Relays are acceptable isolation devices.
No~ deficiencies were identified.
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3.0 Physical Inspection The inspectors examined the control room instrumentation discussed in i
Section 2.0 of this report. The inspectors verified that each indicator and recorder was as documented, had the range recommended by the regulatory.
l guide, and was mounted and located to support electrical and physical separation of redundant instrument channels, j
l Specific identification of Regulatory Guide 1.97 instrumentation was accomplished with vertical green borders of the instrument tag on the.
control panel.
l; No deficiencies were identified.
4.0 Potential R.G 1.97 Type A Variable l
In a letter to the NRC (A09507),_ dated September 11, 1991, NNECO indicates that a comprehensive review of its position regarding R.G.1.97 has been initiated. As a result, several other variables, listed below, are being i
evaluated for potential classifications as Type A variables.
LicenseeL i
internal memorandum NE-91-SAB-235, dated September 23, 1991, concludes I
that the following five variables be classified as Type A.
These variables i
are: LPCI Flow, Torus Bottoms Pressure, ESW to LPCI Differential Pressure l
and Drywell Temperature. The memorandum also concludes, based on its evaluation, that changes could be made that could eliminate LPCI Flow, j
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Core Spray Flow and ESW to LPCI Differential Pressure as Type A variables.
However, in the case of LPCI and Core Spray Flow the' licensee is not comfortable with establishing long term pump cavitation as a design basis.
The licensee expects to complete their evaluation by November 15, 1991, at which time it will provide the NRC with its final position regarding-l additional Type A variables.
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8 5 ~. 0 Environmental Qualification' Master List The environmental qualification (EQ) Master List, Revision 4, dated January 20, 1991, was reviewed to ascertain whether the instruments selected for review were evaluated and tested to the appropriate environmental and seismic qualification requirements.
The inspector noted that the EQ Master List did not identify all-the-containment isolation valve (limit) switches. _ In addition,'the terminology-used in listing the limit switches and solenoid valves was identical, making it difficult to. track these components.
l The licensee did provide a draft copy of a revised EQ Master List, Revision 5, which identifies the missing containment isolation valves.
The draf t copy includes other changes that are being considered to the EQ Master List to provide a complete, accurate and current listing of qualified EQ components located in harsh environments.
This item is unresolved pending.the NRC's review of the licensee's
. evaluation and revised EQ Master List.
50-245(91-20-01) 6.0 Unresolved Item j
i Unresolved items are matters needing more information to determine whether '
an item is acceptable or a violation. An unresolved item is identified in paragraph 5.0.
i 7.0 Exit Meeting The inspectors met with the licensee's representatives (listed in Appendix i
A) at the conclusion of the inspection on October 4,1991. The lead inspector summarized the scope of the inspection, the inspection findings, and confirmed with the licensee that the documents reviewed by the inspectors did not contain any proprietary information.
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l ATTACHMENT 1 Persons Contacted Northeast Utilities Service Company
- P. Blanch, Instrumentation and Controls Engineering Supervisor
- R. Bumstead, Instrumentation and Controls
- L. Davison, Millstone Point-1 PSD Manager i
- R. Joshi, Principal Licensing Engineer R. Kacich, Nuclear Licensing Manager C. Kcusik, Millstone Point-1 PSE I&C Engineer i
A. Maso, Electrical Engineer l
- 5. Dates, Senior Engineering Technician
- P. Santoro, Nuclear Safety Concern Program Director
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T. Thull, Plant Engineer B. Tuthill, Electrical, Instrumentation, and Control Programs Supervisor
- D. Vail, Electrical Engineering Supervisor Northeast Nuclear Energy Company 1
P. Blasioli, Millstone Point-1 Engineering Manager
- J. Summa, Millstone Point-1 Engineering Supervisor
- Denotes those participating in the exit meeting on October 4, 1991.
The inspectors contacted other persons as a matter of course during the inspection.
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