ML18344A411
| ML18344A411 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/29/1979 |
| From: | Dewitt R Consumers Power Co |
| To: | Stello V NRC/IE |
| References | |
| Download: ML18344A411 (107) | |
Text
consumers Power Russell B. DeWitt Vice President company Nuclear Operations General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
- Area Code 517 788-0550 November 29, 1979 Mr. Victor Stello, Jr, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 DOCY..ET 50-255 - LICENSE DPR PALISADES PLANT -
CONTAINMENT ISOLATION NONCOMPLI.AlTCE -
RESPONSE TO HOT::::CE OF VIOLATION This letter constitutes Consumers Power Company's response, pursuant to 10 CFR §2.201, to Appendix A (Notice of Violation) of your letter dated November 9, 1979. Our answer, pursuant to 10 CFR § 2. 205, to Appendix B (Notice of Proposed. Imposition of Civil Penalties) of your letter is being provided separately as reQuested.
Append.ix A to your*letter describes three noncompliances, with proposed civil penalties, for items that Consumers Power Company verbally reported to NRC on September 14, 1979 and reported to NRC in writing by Licensee Event Report 79-037, dated September 28, 1979 and Licensee Event Report 79-037 Rev 1 dated October 31, 1979.
The Company acknowledges management responsibility to establish, implement and audit adequate procedures to assure that containment integrity require-ments are met at all times. We believe we have taken, and are taking, prompt and effective action to remedy the deficiencies in our practices and procedures that these noncompliances disclose. At the same time, we disagree with the noncompliances set forth in Appendix A, as more particu-larly described in the following specific responses to the cited items of noncompliance:
Item l "Technical Specification 3.6.la states that containment integrity shall not be violated unless the reactor is in the cold shutdown condition.
Contrary to the above, the licensee on 424 days (Appendix D) during the period from April 1978 to September 1979, operated the reactor in other than the cold shutdown condition with containment integrity violated. Specifically, the series manual isolation valves in the containment purge exhaust bypass line were locked in an open condition.
2 Item 1 (Contd)
Each day that the facility was placed in other than the cold shutdown mode of operation constituted a separate violation; a civil penalty of $5,000 is imposed for each (cumulative civil penalty $2,120,000.00)."
Res-ponse 1 On September 11, 1979, during performance of a local leak test of Containment Building (CB) penetration 4a (CB exhaust valves bypass*),
a plant employee found the two manual four-inch containment isolation valves** in the bypass line to be locked open. The reactor was in a cold shutdown coridition at the time. After a preliminary investiga-tion, it was concluded that the valves had been opened on April 6, 1978 to perform a test, and that closure of the valves had not been verified by either the test procedure documentation or the adminis-trative check of manual isolation valves that was made prior to resumption of operation. in April 1978. Since the valves could. not be shown to have been closed during the period from April 6, 1978 to September 11, 1979, it was believed that containment integrity was breached during that period, contrary to Technical Specifica-tion 3.6.l. The matter was therefore reported to NRC per Technical Specification 6.9.2.a.(3) (abnormal degradation of the containment boundary).
Specifically, on April 5, 1978, the HEPA filter in the CB exhaust valves bypass line was changed. In order to demonstrate the oper-ability of the replacement filter, i.t was functionally tested in accordance with an approved test procedure. JU.though there were other means of providing the air flow required for the test, our investigation to date tends to show that the isolation valves were opened in order to obtain the necessary air flow through the filter.
At the time of the test on April 6, 1978, the reactor was in a cold shutdown condition, and containment integrity requirements were satisfied. However, we have been as yet unable to verify that the valves were closed and locked after the test was com-oleted, or whether the valves were opened or closed at any time between-April 6, 1978 and September 11, 1979.
The following elements are considered to be key factors related to this occurre!:l.ce:
The surveillance procedure governing the filter testing activities did not have adequate provisions for returning the system to normal,. and had not been signed off to indicate satisfactory completion of the procedure.
The two valves in question were !lot on the valve lineup sheet which was used to verify containment integrity prior to the plant start-up at the end of the refueling outage.
3
~es~onse l (Contd)
Despite the Company's preliminar'J conclusions and the fact that it reported these !llatters as a violation of containment integrity, i::iYestigations to date do not prov-e that the val yes *..rere open at any tine other than April 6, 1978 and September 11, 1979. W:.'lile Our inYestigation of the facts is continuing, at this tine We nust deny any Yiolation and request that it be wi thdraw--n, because of this lack of conclusi -re eYidence. It should neYertheless be clear that the Conpany regards the la.ck of adequate documentation and the demonstrated weakness in its procedures in this instance to be a ver*y serious ma~ter. It is beyond q~estion that main-tena..."lce of containment integrity during oper-ation is of vital importance, and there must be adequate assurance and v-erification of contair..ment integrity. ~fuether or not containment integrity was actually breached in this instance is beside the point in terms*
of corrective action. It is clear that our procedu:-es and the way they were i::nplemented in this instance coul*:i have allowed contain-ment integrity to be inpaired for the period in question. Accordingl;;,
the Company undertook i;:nmediate action, prior to receipt of the Notice of Violation, to remedy the deficiencies in its procedures and documentation so that containment integrity will be properly mai::i-
-:air:ed .s.nd doc~e!lted i:i the f .x:ure:
1
( 1) Upon discovery, the affected Yalcres wer-e closed and loc~.\:ed in the closed position;
( 2) The sUI"reillance procedure which governs the fil te!" test-ing was revised so that rett:.rn to service requirements are adequately addressed.
(3) The containment building integrity checklist was i::m:lediately modified to require verification that these val Yes are locked in the closed position. A master checklist of all containr:ent
- penetrations was prepared by an independent consultant, MFR As~ociates, Inc (Report - without photographs - is attached hereto as Exhibit 1), and verified by Consumers Power Company staff. The recol!l!Ilendations of the MFR report are being imple-nented. The master checklist was prepared by MPR from nla.nt drawings and ser*res as a single reference noint for the - Yerifi-cations described below. The checklist in;ludes the penetra-tion identification n1.ll:lber, a :piping diagram which includes all isolation valves, -ralve number-s, valve posit:..ons and other pertinent info~ation. ,Each accessible* penetration was physically located, sighted a..~d in some cases photographed, and then checked off the master checklist. The accuracy of the checklist, with respect 'to the piping diagram, Yal 1re positioning and nuzbering, penetration identificai;ion number and other :pertinent data, ~as verified against the actual installation. As necessary, the checklist was :narked to reflect any differences between it and the actual installation.
- One penetration is not readily accessible and was r:.ot 7isually checked.
4 Resnonse l (Contd)
(4) The corrected master checklist was used as a basis for the following: *
(a) Verification of the start-up checklists used prior to start-up to verify containment isolation valve positions.
(b) Determining whether differences between actuai instal-lations and the checklist, if any, have any safety significance.
(c) Determining that plant drawings and actual installa-tions agree.
(5) All plant operating, maintenance, health physics, chemistry and other procedures are being screened to determine which of them may affect safety system requirements, including containment integrity. An estimated 900 procedures require screening. A detailed review of those procedures which affect safety system requirements will be performed to assure that plant initial conditions are properly addressed and that return to service steps are sufficiently e:iqilicit to assure that safety system requirements are reestablished upon completion of all such procedures.
( 6) The review process described in ( 5) will also be applied to system checklists.
(7) To provide additional assurance of a meaningful review, the review process described in (5) and (6) above is being performed by a special task force (the "Palisades Management Review Task Force";
the program plan for the task force is attached hereto as Exhibit 2).
(8) This event has been reviewed with applicable plant personnel. The requirement to exactly follow procedures (e.g., to obtain administra-tive reviews when required) was stressed.
Consu.~ers Power Company will complete all of the. uncompleted actions described above prior to plant startup. Although we are denying this item of noncompliance based on the facts as presently known to us, it might be substantiated as a result of our ongoing investigation. If so, it should nevertheless be reclassified as an "infraction" based on the Commission's cri te:da for distinguishing behreen "violations" and "infractions" ("Criteria for Determining Enforcement Actions,"
December 31, 1974). In this connection, please refer to our response to Appendix B of your November 9, 1979 letter.
5 I-tern 2 "Technical Specification 3.6. 3 requires that prior to going critical after a refueling outage, an administrative check will be made to confirm that all manual containment isolation valves are closed and locked.
Contrary to the above, prior to going critical after the April 1978 refueling outage, an administrati Ye check did not verify that two manual containment isolation valves for the containment purge exhaust bY!Jass were closed and locked as required. This is a Violation (Civil Penalty - $5,000.00)."
Resnonse 2 The response for item 1 above describes this eYent and its corrective action as well. Palisades Plant Technical Specification 3.6.3 requires that prior to going critical after a refueling outage, an administra-tive check will be made to confirm that all manual containment isolation valves are cl8sed and loc~':.ed. Although the required administrative check was performed, the two valves in question were not on the check-list. This deficiency has been corrected. Constm1ers Power Company requests that this item of noncompliance be reclassified as an "infraction," in accordance with NRC's published enforcement criteria and description of noncorrrnliance categories ("Criteria for Determining Enforcement Action," December 31, 1974). In this connection, please refer to our response to Appendix 3 of your November 9, 19T9 letter.
Item 3
"~echnical Specification 6. 8 .1. c requires implementation of procedures for surveillance and testing of safety-related equipment. Health Physics Procedure H.P.6.27 governs testing of inplace HEPA and charcoal filters in safety-related systems pursuant to Technical Specification Table 4.2.2, and requires notification and sign off by the Shift Supervisor and the plant Health Physicist on completion of testing.
ContrarJ to the above the required notification and signoffs were not completed after the licensee tested filters in the containment ventila-tion ex.~aust DY9ass line under H.P.6.27 on April 4-7, 1978. This is an infraction (Civil Penalty - $4, 000. 00) . "
Resnonse 3 Consumers Power Company agrees that the alleged item of noncompliance did occur. The following corrective action has been taken:
(l) The test procedure was revised to incorporate the requirement to Yerify that the containment isolation "Tal ves in question are locked in the closed position prior to return to service.
This action is complete.
L
a Resnonse 3 (Contd)
(2) The revised test procedure has been reviewed with applicable plant personnel, including shift supervisors and personnel responsible* for such testing, to whom the importance of exactly following the procedure has been stressed. This action is complete.
(3) The reYised test procedure is one of the procedures that is being re'riewed by the ?alisades Management ReYiew Task Force pursuant to j:laragraph ( T) of Response l. 51.is reYiew will be completed prior to plant startup.
8 UI!l!!lar'T
- I-Toncompliance Item 1 is denied and should be withdrawn for lack of sufficient e'ridence. The Company's investigation of the i-cem is not yet complete. E:rtensi-re correctiYe action was set in motion,
- .
- -icr to :-ecei:;it of the Jotice of Violation, and c:hat ac-cion will be coDpleted prior to plant startup.
- Nonco:::pliance Item 2 is admi:~ted, bm:; should be reclassi:f'ied as an "infraction," in accordance with NRC enforcement c::::-i teria. '!':-ie cor~r:=cti . .,e actio!l :'or this i -:e~ has be~n corr.:ple-l:.eC.. .
- ~roncoI!!pliance Item 3 is admitted. The correctiYe action for this item has been completed except for Task ?orce re'riew, which will be completed prior to plant startup.
The Company also seeks :.:-emission or mtigation of the ciYil penalties proposed for the three cited noncompliances. ?lease see our concic.rrent response -co Appendix B of your NoYember 9 letter.
Yours ver'J truly,
/s/ R B DeWitt
?. 3 JeWitt ilice Presicient
MPR ASSOCIATES. INC.
Exhibit J.
PALISADES NUCLEAR POWER PLANT INDEPENDENT REVIEW OF CONTAINMENT PENETRATIONS MPR-639 Volume I of II Volumes Report to Consumers Power Company Jackson, Michigan Original Issue: November 5, 1979 Revision 1: November 15, 1979 1140 CONNECTICUT AVENUE, N. W. WASJilNGTON, 0. C, 20036 202
- 659-2320
M PR ASSOCIATES. INC.
TABLE OF CONTENTS VOLUME I I. Introduction II. Summary III. Appendix Procedure No. MPR-98-56-1 (Rev. 0),
"Procedure for Locating and Identify-ing Containment Mechanical Penetrations and Isolation Valves" Addendum 1 VOLUME II Photographs of Containment Penetrations i
MPR ASSOCIATES. INC.
I. INTRODUCTION The purpose of the report is to present the results of an independent check of the Palisades Nuclear Plant mechanical penetrations and isolation valves. This check was performed by MPR Associates, Inc., with the assistance and cooperation of the ~alisades ~lant staff.
The independent check of the containment penetrations and isolation val_ves was performed as follows:
- 1. A procedure for performing the independent-check was prepared (see Appendix ).
- 2. A master check list of mechanical penetrations and isolation valves was prepared using the documents referenced in the procedure. These documents included the: applicable portions of the FSAR; applicable Palisades procedures and check lists, applicable P&ID's and the containment building penetration drawing.
- 3. All accessible containment penetrations were physically located and visually examined on both the inside and out-side of the-containment.* Temporary markers (consisting of di~monds) with the penetration number inside were placed on the accessible penetrations. The lines were traced to locate all branches and valves which could affect containment isolation. Photographs of each
- I.l
accessible penetration.were taken both inside and out-side of contairunent. These photographs are presented in Volume II of this report.
- A~ The as-built configuration of the penetrations and ..
isolation valves were checked against the master check list. The*master check list was revised as necessary to reflect,fhe as-built conditions.
- 5. The referenced documents were checked aga.inst the master~ check list and the chan*ges which were required to bring them into conformance were identified.
- 6. A list of all containment building mechanical pene-*
tration valves, pipe blind flanges, and pipe caps whicl_1 a~e part of the containment integrity system was prepared.
I.2
MPR ASSOCIATES. INC.
II.
SUMMARY
A. Independent Check of Containment Penetrations and Isolation Valves
- 1. The initial visual inspection of containment penetrations and walk-down to locate and identify the isolation valves was performed on October 15, 16, and 17, 1979. This inspection was performed by MFR and Palisades QC personnel. Temporary markers wer.e placed inside and outside contain-ment and photographs were taken.
- 2. The master check list was updated based on the results on the initial visual inspection and walk-down. A second inspection and walk-down was performed by MFR and Palisades operating personnel on October 23 and 24, 1979. The purpose of the inspection and walk-down was to confirm the accuracy of the updated master check list. This second check was considered necessary because a number of differences were noted between the original master list and the as-built configuration, and because it was difficult to trace the pipes in several congested areas outside the containment.
- 3. The updated master check list of the containment penetration and isolation valves is presented II.l
in Tab.le II-1. This .table contains the following information:
0.
Penetration number and classification (as given in the Palisades.PlantFSAR) 0 As-built.donfigura~ion showing all valves which could affect isolation 0
The applicable P&ID number and system
.. identification 0
The dates of the inspection and the photographs reference number to Voli.irne II 0
The identification of each valve and its normal position during plant operation The legend explaining the valve and piping symbols is presented iri Figure II-1~
- 4. Preliminary conclusions and recommendations based on the result of this independent check of contain-ment me.chariical penetrations and isolation valves were discussed and reviewed with Palisades per-sonnel .at meetings on October *17, 24 and 29, 1979.
B. Conclusions and Recommendations *
. 1. All manual valves which should be normally -closed
- during normal operation and which were not being used during the refueling shutdown were found to be closed .
. _2. There are a n~er of differences between the as-buil t configuration and the references listed in the Appendix which require resolution. These I.I .2
differences and the recommended actions are presented in Table II-2. *A preliminary copy of the list was reviewed and discussed with Palisades representatives on October 29, 1979. This list was updated again based on discussions with Palisades personnel on November 7, 1979. The significant differences are as follows:
- a. It was thought that the pressurized dead weight tester line and the reactor coolant system sample line went through* the contain-ment at penetrations #20 and #21, respec-tively. Actually, both of these lines go through the containment at penetration #40.
Accordingly, the reactor coolant system sample line penetration is now designated as penetration #40 and the pressurizer dead weight test line penetration is designated as penetration #40a.
- b. The actual configuration of the contain-ment pressure instrumentation lines which go through penetrations #17 and
- 48 was different than that shown on the reference drawings. Specifically, (1) only one line was shown to go through penetra-tion #48 instead of four which is actually the case; (2) penetration #63 which is shown to be an instrument line penetration is actually a spare; and (3) the isolation valves for the pressure switches and pressure transmitters were not shown on the applicable P&ID.
- c. Pressure taps not shown on the applicable P&ID's were found on several lines (e.g.,
- 25 - Clean Waste Tank Vent to Stack) .
- d. There w~re several instances where vent or drain lines with manual valves in them were found which were not shown on the applicable P&ID's (e.g., vent lines on the main feedwater lines going through penetrations #7 and #8).
II.3
- e. In some cases valve identification tags were missing and in several other instances valves had what appeared to be tags with the wrong number (for example, a tag was missing on the test valve on the service air line going through penetration #10 and the test valve on the purge air exhaust sample line going through penetration 4a should be identified as 507VA rather than 506VA).
- 3. All valves, pipe blind flanges and pipe caps which are part of the containment integrity system should appear on the Containment Isolation Check List (CL3.3) and should be tagged with a special colored tag which identifies the valve as containment isolation valve. Palisades personnel agreed to prepare dark orange lamicoid tags for this purpose.
- A preliminary list of components for which special tags are required was reviewed and discussed with Palisades representatives on October 29, and November 6, 1979. The updated list which lists all of these components is presented in Table II-3.
- 4. The Containment Penetration drawing (M-140) appli-cable P&ID 1 s, Palisades procedures and valve check lists, and the Palisades FSAR should be revised to conform with the as-built configuration shown in Table II-1. In this regard, a marked up copy of the Containment Penetration Drawing (M-140) was presented to Palisades representatives on October 29, 1979. The other actions necessary to update the.
P&ID's, Palisades procedures and valve check lists, and the Palisades FSAR are presented in Table II-2.
II.4
- S. Permanent identification numbers should be affixed to the inside and outside of every accessible penetration. This will facilitate future checks of the containment penetration and isolation valves.
- 6. There is an outstanding deviation report {QP~79-19) pertaining to the Containment.Air Sample Line (Penetr~tion #28) whicih sho~ld be closed.out. Since this line may have to be modified as a result of
- implementing the "Lessons Learned from TMI-2",
consideration should be given to capping the line until the.necessary modifications are designed and implemented.
- 7. During discussions with Palisades personnel on November 6, 1979, we learned that several Facility Changes (FC's) arid Specificati6n/Field Changes (SFC' s) which ~10uld change the as-built configura-tion of a few penetrations had been or were scheduled to be implemented during the 1979 refueling
.outage . . The changes are presented in the Addendum to this report at the end o*f Volume I. As these changes are implemented, the applicable portions of the master list (Table*II-1) should be changed to show the as-built configurations *. The reference documents should also be updated to be consistent with the as-built configurations and master list.
II.5
TABLL .Il-1 MAS HR LfSf' or f'M. [~;\DES CONTMNMENf MECHANIC/'\L f'ENURArIONS SHEET _1_ OF _fl_
PENE- LOCATED. INSPECTED TRATION CONF lGURAT!ON P&ID SYSTEM .
AND PHOTOGRAPHED NUMBER 1--------.----"""T""..,...--------~---1 NUMBER ArlD OUTSIDE CONTAINMENT INSIDE CONTAINMENT OUTSIDE INSl'.lE CLASS
(?
IO*IS*7'f 10*1"*19 IO*Z.S*7'7 JO*Z4*7'i'
,__,~ .c,v~cv iaoe .* I
~
1807 sz" 48" PURGE SUF'PL"T" AIR 0-1-l(s) 0-1-z
- 0-1-a
!* 1-1(
3
)
<-CJ1*-soevA l.!.I
\O*IS* 7q IO*!G*79 JO *t3*7'f IO~Zf-1"1 r-lO Flt!.1..IE,. ~
SAFEiY.
VA~VE'S z: ,------.. M*205 MAllJ SiEAM O*t.* I !* Z* J
. ---1. .c."'.._v....,~ M*207 L.JNE
( SG E 50A)
~-s-1 4*
- Wt.~T-110 MS (CI)
\O*IS*1.:j IO*IG*/q IO.*Z3*7q IO*Z4*7'!
~o ~~=~v*
v~ves
,------.. ,49* IA*20S M*207 MAI~ SiE.AM 0*3-1 !* 3-/ .
J L.ll>IE o-3-e I
4" (S~ E SO 13) ..
c: - E."Si'.
111 MS (c.1)
/0*15'*1'1 /O* IC*/'1' IO*Z::!>* "1'7 IO*Z.4'-1'f 4 0-4-1 !-4-1 5'2 PURGE AIR 0 - 4 *Z:
M*Z.18 0-4*3 EXHAUST I
48" 0*4-4 (Al) 10*15"*7'7
- I 3"
_ 10!._V~S l~Y~S 1
l "i...:~ 1 L.c~
10*'3*i'f 4A . W:: l '/i*507VA M*210 PURGE EXHAUST SAMPt..E" 1...1 t.JE' AIR 0*4A* I IJ/A L:J (AZ.)
NOTES! (t) PENE.IRATIOH C1...ASS NUMBE.R IS 'BASE.'C OIJ !'SA~' TASLE. s.e (2) DA.it.S Pt,1\1(.\RATIOt.J.S Y'/E.E!,'E. 1..0CATt:D ~NCl VISUALL'( INSPCCT'CD.*
(3} P~OiQql!A.P\.\ cgo::s "E.n:.eEIJC.~ HUMe.t:.e iO '/01..UMC z*: 0' O*..!TSIOE.. :i:' llJS10t:: ~
l"ll<:ST NUMe.E:~ \~ PDIC.T;cATION NUMl!.E.C ~ lo.NO. ::;i::oNO NUMe~e 15 r'11oroc;~APli '"l.lr~~w2.
(4) t-'1"""-IUA\... MO:::IV ~YP"""::; VAl../l.S *;111..1.. c:: l:?t::.Pl..AC.~0 *111-:-11 MQTrJ.:: CPE:J2ATW VAL~*i.;,:;,
- St.~
Atlt:.E.lJOWM A.i ~*m Or '/01..t.iM~ :r.
TABLE 11-1 MJ\STER LIST OF PM.ISMlES CONT A!NME.rff MECflMllC1iL fT~IURAf IONS SHEET _z_ OF~
PENE- LOCJ\TED, !NSflCTED TRAT!ON . CONFIGURATION P&ID SYSTEM AND PHOTOGRAPHED NUMBER NUMBER AND CLASS OUTSIDE CONTAINMENT INSIDE CONTAINMENT OUTSIDE ms IDE NC !O-IS-1'i J0*1~*1'i .
~ 1 I/'~S~7MS 10*2.3*1 q . 10-24.,.,
cv*
0771.
f l..C
,. -~
NC.
s* cv-4 07fil7 1a* M*207 SG. (i:SOA.) O*S-1 1-S*t
~~ M*2ZG BOiiOM 61..0W (CZ) av-
-~
NC t L.C I/!-JC . l'~SGSMS
~
IO*IS*79 10 *Z.3-1q I0*1 '-*1'i IO* Z4*19 0770 I -
cv-+
I 12* M-C~07 SG (:SO 6) O*G-1 I* 6-1 G 07GS *
- 7 M*ZZG BOTTOM BLOW (cz) 10-15-1'! 10*16*7'1
, ..~N2J6R*0104 IO" IO*Z:'.3-"7"1 IS'!N218R* 0702
.30' FEEOWA1CR TO 7
- I ~ M*i!07 0-1-1 !*7- J J"""""---, - ~
.. IS" j 16" . S~ ( c SOA.)
- v..*
,.-- 74i.F'w' Cl-/JCl.GO F!T"rlNGo("'r'1P) /
(CJ). S~!: NO~ S 10~ 15'*1'f 10- I~* 7'?
G"*N2.ISR*070~ IO*Z3*7"1
..---,-....,.1.-
co*
18"*N218~-0701 !O" FEEDWAiE'Z "TO !'*8-1 8 __,~
~
M*207 .O*S'-1 18" J 1e* sG(a-soe)
"?*"I FW~:
$E.ti.ion: s--"
t l
(c1) i NO~.-r.1 (s) A.NOTHE.'i?.
C.Hl'-.AC,O
\SOl..ATIO!.I F"liTli.JC:. Wll.I..
VAi.Vt. Wll..1.. ~e:. ACDE:..O 11.1- .Sc:.R1e.s. WITH Tl-IE oeA1i.J VALVf.. A"JO n!E:
ee. et.f'l.AC.W G'f A <:.AP. se:E. AOOEl.ICUl'VI t\T =:>.10 Cr 'iOUJM~ r .
F"o~* Ce:T"AIL..~,
I t
~
T.'ELE l l-1
~flSTfR LISf OF Pf1LIS;\OFS CONTWIMrnr ~[CHMUC;il f'Erl[fRMIQrlS.
SHEET _.9_ OF_Iq_
PENE- LOCA rm. l~ISPECTED TRAT ION CONFIGURATION P&ID AND PHOTOGRAPHED llUMBER SYSTEJ'1 NUMBER AND OUTSIDE CONTAINMENT CLASS INS IDE CONT A!NMENT
. OUTS IDE INS IDE IO~IS-7'! 10-1'--l'r lo*z.3-1~
~ r* .. - SPARE o-q-1 r~ "!-/
(N/A) 10-IS*'"l~ 10* IG*'"l'r
/O*Z.3*7'l 10 Z~2"3
. I ....
e!t2ZCAS I
I 12" 2" M*21Z SERVICE AIR 0-10-1 I-10-1.
"" .. 1..c"""
1.CJ [14Z.C:.A l.:.J (Ae) I 10-1s-7q 10-1,,7.,
IO*Z3*1, NO II 1Yi'*22.3
~
- Y:
~
~""'
I lI
~z* Wi' M*2ZI
- coNCcNSAi'E 1'0 Sl*llE:lO COOLING 0-11-1 o-tJ*Z
! *fl* I c.v SURGE TANI(.
oq3'!
LC:' :1'! ~~6CO
~
- S3<.A*C:C *
$~~ "IOTI:, C.
(C2.)
f,\Bll I 1-1
- 1;iSU R l.l sr tlf" r,\Lf s;*,rr:s corn A[ NMt ~n :1EU!All I (,\L ru:URi\f [()NS SHEET ~OF _B_
PEtlE- LOCAfED. !NSPECT~D TRAT lON CONFIGURATION NUMBER f'& l D SYSTE.11 AND PHOTOGRAPHED 1--~~~~~~~~,......~~~-...~~~~~~~~~~~~--iNU~SER AND CLASS OUTSrDE CONTAINMENT INSIDE CONTAlmlENr OUTSIDE INS IDE
,~
0 IO*ic;*7'l IC - e"
- ~l---5 av osc;q NO
-:; 8. ;--l. f----:S CV 0&&5 SERVICE WATE.li:
re. NO M*ZOB 0- 1:e-1 'r-1'2*1 S.UPPL'T' 8
.I
........... ~
1e* cv osc;z I] NO 10- ~ti----,'
CV0870 (x) SE.:: No T'E.. 7 10-JS*l'f 10-1'-*7'1 CV0843
--.. IO*Z3-1'l' NC.
z3e
,, .."r - -j~f-~
CY08G7 410 10*
SE.!!:.NO~ e 57'Z SN'S NO SEF\'VIC:E WA.TE.I:!
13 M*zoa 0-1:3-1 r-1'.3- I
.~ l ~E"TUZN 0-13--z.
- '.:j:l~itr-cv oae" I"
'~~ "-"
1:0
-~ ....
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NOTCS; (7) T~e. sE.evic.:: WATE.e SUPPL'( l.INE.. INSIDE. CONT-"INMENT WAS :"'\OOIFle:.O ... FTE.2 -;--..:<:, 10*\Co*n WA\.X oo*N....i.
PIPllJC. l'"Oe rl~E. \o\OSE:S WA.S AOOED. SC:E.. AODE.NCUM A* ~l.!0 o~ >/OLUMt: I F"oe C~1"~1L~.
(Bl \aE..VIS?:.0 C.ONT,O..l>IME.1,rT INit:.~e1~ C.HIO.Cl::l.IST (C:...3. :.) WILL etQu1~e: VEJ..lr LIN~ 10 i:.e:. CAPf!:C.
f1iBLE I 1-1 MASTER [!ST OF PALISADES CONTAIWUr ~ECfWHCAL f'f}IEfP.AfIOrlS SHEET _s_ OF -1.:L PENE- LOCATED, lllSPECTED TRATION CONFIGURATION P&!D AND PHOTOGRAPHED NUMBER AND*
~------------'!""""' ____________,NUMBER SYSTEM CL.ASS OUTSIDE CONTAINMENT INSIDE CONTAINMENT .OUTSIDE INSIDE lO*IS*7"1 IO*JG;*1'f 10* L3*11 CO~PONENT 14 M*i:?O" *0-14* I I* 14*1 COOLING WA"T"EI?
1o~es1.oq1occ CV 0'!10 IN 1..C f.1"*507CC w .
(cz) 10*1.!Vi"I 10*1G*i'I 10*23*/'1 NO 15
~i CY0'!40 1<0*
M*20"1 COMPONE'NT COOL.II.JG. WATER 0*1s-1 I* 15* I OUT (cz) 10 *IS*1'f I O*lt:- i'r NO.
. llO M*207 O-IG-1 !- I'°- I sueFAcc: 61..0'rV cowi..i (Cl) 10-1~n 10-1"-n IO*Z3*i"f
}w COIJTAJ "-IMENT 0-li* l :r:-11-1 17 M*Z18 PRE.SS URE 0* li*Z 11.iSTRUME.i..JT- o-li-3 ATIO.._.
(NOT GIVEN) j I
t 1
l
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TiiBLE 11-1 MASTFR LIST nr: PM IS/iDES CONT A!NMENT MECHl\N I CJ\L PENE iR1UIONS SHEET -'°-OF~
PENE- LOCATED, INSPECTED TRAT ION CONFIGURATION P&!D . AND PHOTOGRl\PHED NUMBER NUMBER SYSTEM AND OUTSIDE CONTAINMENT INSIDE CONTA!NMENT OUTSIDE !NS !DE CLASS 18
~.,
c~ 11 I
48 J
T:..%
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TUBE
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10-24-n IO*Z4*n
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-u .. 0-1'1-4
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QQOk?:*IS 1:1.0S~Q: g* -
OPEN 'NHlW coo~ -J~"
IS OP~W) PSA (X) 10-1c:;*1"1 IO*IG:71 IS" eo I ..- SPARE Q*Z0-1 !*ZO* I (N/A) l0*1~*7'f IO- IG-7"1 II!'
e, 1 E-re' - SPARE O* Zl-1 l*ZI- I I*
(~/A).
f
- l'
j" TABLE 11-1 MASTER LIST OF f'.~LIS1\DES CONTAINMENr MECHANICAL rENl£RAT!ONS SHEET _7_ OF _1_'.:L PENE- LOCATED. INSPECTED TRATION CONFIGURATION P&ID AND PHOTOGRAPHED NUMBER SYSTEM AND 1--------------..--------------i NUMBER OUTSIDE CONTAINMENr INSIDE CONTAINMENT OUTSIDE INSIDE CLASS IO*IG*7'1 PI 037* !Cl* Z~*i'?
NC:. r;;:rJ_' r <! V
~ .. .3018 REOUNOAl'JT H. P. SAFE:TY O*ZZ*I I-zz-1 INJECTIOIJ NC.
=*
fAD_'!iJ'
~ .. 3036
' c.v
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RV3Z~4 (x) ,.
/O*IG-i'T JO .Z4*f"I H.?. SAF;TY o-z:.3- I !-Z3-I l~..lE'C.T\01...1 (X)
IO-IG-7'f IO*IC-/Cl IZ" Z.4 ] - SPARE O*Z.4- I I* e~ -1 (N/A)
IO*lb*79 IO-\i:;*i~
G47CRW IO*Z3-1'f PT ~~
OG NO NO NO CLEAN WA S1'C:
~ ~
i --
12.
z" RC.C.E:IVE.R 2S' t.1*210
'iAN"<:: VENT o-zs-1 I *e=- J c.v10G4 CV IOG5'
~ TO Si AC I:::
LC 1*:s1ace
&.:.I (ca) l L __
- t .. ~.
TABLE 11 *l MASTER LIST OF.PALIS1iDF.S CONTAINMENT ME CHAN I CAL PENE TR;\f l ONS SHEET _s_ OF~
PENE* LOCi\TED, INSPECTED TRAT!ON CONFIGURATION P&!D r'1ND PHOTOGRAPHED NUMBER SYSTEM NUMBER AND OUTS !DE CONT AI NM ENT I NS !DE CONT AWM ENT OUTS IDE INS IDE CLASS IO*G*"J<i 10 *16*7'1' IO*t3*°"'*
NC.
ZG 1"-ez~
~
~
~
~
~
I 1 l J 12*
a' M*ezz. NITROGEl-4 TO QUEkl C.H TAW~
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NC.
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I L.c1G04VA I
12" 6"
'I
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L..11*.J'E O*Zl*I I* Z7* I LefosvA (X)
IO*t6*7'1 10*16* 7'f sv
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A
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ea E ..,, ,.,
~ A I , ~ . ..._:~
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O*Zi!-1 I-Z8'-I l
IJ r-z.s -z AUX 6Ull.OING ANAL.'\"Z.l;l!:. 5AMP* ¥: SVZ40Z.*N L.11'1<:5. PANEL.. ,,,.. -. .
GIVE.'N)
(O*IG*l'l IO*IG*7'J.
1a*
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NO"i"t:.:;,; ('!) THIS .L.INE: WILL !!.E.. CAPPE.0 ..1\J::.T 01..lTS\OE.. CONTAINM'E1'11. SO.E: AOCE.1'10UM P..i :.!-JO OF" VOLUMe: J:
F"O R Oe:T Al \.S. *
' 1 .
TABLE ll-1 MASTER LIST UF rl\l.ISADES CONTAINMENT MECflAN I Cr\l f'ENE TRl\T I OtlS SHEET __@__ OF _B_
PEN£- LOCATED, !NSf'ECTED TRAT!ON CONFIGURATION P&ID ANO PHOTOGRAPHED NUMBER SYSTEi'1 NUMBER ANO OUTSIDE CONTAINMENT INSIDE CONTAINMENT OUTSIDE INSIDE CLASS I0*1~*7"f 10* H;,,-,q la- 't.3*1'f m
i..c.) [<00.'ZVA
.._I.~ ... ,~* W-e." ~ GC:,IVA
. IL.RI I
""' " ~c:.-
l..C.. :~0.3V.4
. I i.e. INSTE:.UMENT L.fNc O"""'*I I*~-1 (x)
JO*IG-1q 10 *IG*i"f ID*Z4-1'1 NO
~7 a* -
I
~
av- - 10$;
J J?
3' M-2-10 CLeA'-' WASTl:
l?'!:'CSIVee IAIJI<::
o-~1-1 0*~"7*Z I-67-1 I*G7* 'Z..
.. PUl..!P F?ec1iz.c.
L.C: ' :sl!iC:.ZW' t..:.I (cz) l0*16*i"t 10-1i:;.7.,
.. 10~'%.3* '"
tJC I.JC GS Ji ~~ ~ jg* **
M*218 Ale SUF'l'.'L'f ro* Are 0-611*1 I-Gs- r
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f!.OOM l.C 1!1>05VA t.!J (Al) 10-11:.*'" 10*1~*7"!'
I0*~3*7'f NO
~
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. 12'
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fUMf' WASTE TAI.Ji<:
SUC.TICU O*'-"l* l !*G'H
TABLl Ir*l MASTF.R usr 11F r,,usr,ors CONTAINMENT :-1ECHMl!Ct'1L f'ENEfRflT !ONS SHEET -15_ OF~
PENE- LOCATED. INSPECTED TRAT!ON CONFIGURAT!Grl P&ID AND PHOTOGRAPHED NUMBER* NUMBER SYSTEM AND OUTSIDE CONTAINMENT !NS IDE CONT A!NMENT OUTSIDE INSIDE CLASS IO-tC.*1'1 I0-~*1'f .
70 I
1z.'
- S:PAeE' 0-70-1 l-10-J
- (N/A) 10-1~* 7"f 10*\,*1'1 IZ' 71 II - SP4i:e 0-71-1 J:~")l-1 (N/A) 10-1.:;-i'I IO*IG*1'l 10*2.:0*1'1 IO*Z::.*1'7 RE"AC'l'O!l..
. ~l.C. ie* R" ~1..s n - .,. ~
J r ~
1-.1-221 REFUELING 0-7Z*I . I- 7Z- I
\ISSFi' 117SF!' CAVITY C~ti.J r
L.C 1 1'! el!iSl'f'
- - ~.
(Ae)
[O-IS*7°" IO*IC:0*'7'f IO*Z.3*"1'1 12 ~*'
7':3 i: ~I - SPAe:c 0*13*1 t-1~-J L.e; *Vet so9v~:;
Ll.I (N/A)
Sheet 1 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 1. None 2.&3. a. Procedure for ensuring Bypass Valves Mieras FC's 445-1 and 445-2 will result in manual (illMS & llO~S) are ciosed during nor- *valves being replaced by motor operated -
mal operation should be identified. valves. Modification should be completed by end qf outage. MOV's should be added to CI check list and tagged with special tags.
See Addendum 1 at end of Volume I.
- b. Change P&ID-M-205 to show correct Done. Rev. 21 of P&ID M-205 shows correct MSlV and bypass valve numbers valve numbers.
- c. Include description of Bypass Valves Palmer in FSAR
- 4. None 4a. a. Tag on test valve should be corrected Mieras (valve # should be 507VA not 506VA)
Sheet 2 Of
- 19 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RES PON-No. ACTION ITEMS SIBILITY. STATUS 4a. b. Isolation valve ID#'s should be added Mieras cont'd to P&ID M-218
- c. Penetration should be given a classif i- Palmer .
cation (A-2) and described in FSAR
- d. Valves lOOVAS & lOlVAS should be added Mieras Complete to Containment Integrity Checklist
- 5. None
- 6. None 7.&8. a. Drain valves should be given ID#'s and Mieras Done. Drain valves hav.e been identified as t~gged with normal tags (Black). Also 746FW and 746AFW adding another drain valve in service
Sheet 3 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RES PON-No. ACTION ITEMS SIBILITY STATUS 7.&8. b. Drain valves should be added to P&ID Mieras cont'd M-207
- c. FSAR should note that check valves are Palmer in parallel
- d. Procedure fol:' ensuring valves are Mieras closed should be identified
- 9. None
- 10. a. Test valve 142CA not tagged (This will Mieras be covered by special isolation valve tags)
- 11. a. Test valve 536CD not tagged. (This Mieras will be covered by special isolation valve tags)
Sheet 4 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 11. b. Second test valve should be given an Mieras Done. Valve number is 516A-CD. Tag in cont'd ID# and tagged with a special isola- preparation tion valve tag
- c. P&ID M-211 should be changed to show Mieras test valve 12.& a. Vent valves should be given ID#'s and Mieras
- 13. tagged with normal tags {Black)
- b. Vent Vqlves should be added to P&ID Mieras M-208
- c. Procedure for ensuring vent valves are Mieras closed should be identified
- d. Pipe for in-containment fire hoses Mieras will be connected to this penetration per Facility Change 407. See Addendum at end of Volume I for details
- 14. None
Sheet 5 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENE'l'RATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 15. None
- 16. None
- 17. a. Isolation valves should be giveri ID#'s Mieras and tagged with normal tags (Black)
- b. Valves.should be shown on P&ID M-218 It is the policy at Palisades not to show pressure instrumentation line (and sample line) isolation valves on P&ID's. These valves will appear on the appropriate valve check lists
- c. Procedure for ensuring proper valve Mieras position (LO or NO) and cautibning that these valves are part of contain-ment boundary should be identified
- d. Penetration should be given classifi- Palmer cation and described in FSAR
Sheet 6 of* 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RES PON- -
No. ACTION ITEMS SIBILITY STATUS
- 18. a. Fuel tran_sfer tube isolation valve Mieras This 48" diameter valve is identified by its should be given ID#. name rather than by a *number.
- b. Procedure *for ensuring valve is closed Mieras during normal operation should be identified
- 19. a. Procedure to check integrity of Mieras personnel lock sho1,1ld be identified
- 20. a. This is a spare penetration. I t does not have the PZR dead weight tester line. This is one of two lines coming out of penetration 40.
- b. P&ID M-201 should be revised to show Mieras correct penetration number
- c. Table 1 of Local Leak Test Results Mieras should be revised to show correct '
- penetration number. ..
0 Sheet _ i _ of _ l l _
TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 20. d. Containment Integrity Check List should Mieras cont'd be revised to show correct penetration number
- e. FSAR should be revised to show correct Palmer penetration number
- 21. a. This is a spare capped penetration. Mieras &
It no longer has the NSS sample line. Palmer This is now one of two lines coming out of penetration 40. -
NOTE THAT COMMENTS B,C,D,&E ABOVE
(#20) APPLY TO THIS PENETRATION AS WF.LL 22.& a. Procedure for insuring isolation Mieras
- 23. valves in pressure lines are open during normal operation should be identified
- b. Procedure for ensuring sample line Mieras In the short term until a decision on the valves are closed during normal opera- use of sample lines is made based on TMI-2 tion should be identified considerations, these valves will be locked closed. They will be added to the CI check
Sheet 8 of 18
- TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS 22.& list and given special colored tags 23.
- c. Add pressure lines and sample line to See comments for 17.b.
P&ID 1 s M-203 and M-204
- 24. None
- 25. a. Add pressure tap and isolation valve See comments for 17.b to P&ID M-210
- b. Procedure for ensuring integrity of Mieras pressure tap should be identified
- c. Test valve 512CR has no ID tag (This Mieras will be covered by special isolation valve tags)
- d. If cap on drain stub is not welded, it Mieras should be tagged and added to CI check list
- 26. None
Sheet _9__ of _!L TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RES PON-No. ACTION ITEMS SID I LI TY STATUS 2 7. a. Arrangement for ILRT isolation valves Miera:s
- ILRT contiguration will be added to P&ID should be shown on P&ID or other con- M-218 trolled document
- 28. a. Palisades deviation report OP-79-19 Wong Specification/Field Change (SFC) 79-23 calls should be closed out for this line to be capped
- b. This penetration should be given a Palmer classification and described in FSAR
- c. Valves on Aux Building Analyzer Sam- Mieras pling Panel should be given ID# and tagged
- d. Procure for controlling position of Mieras these valves should be identified
- e. P&ID M-224 should be revised to show Mieras as-built configuration
- 29. None
Sheet 10 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETHATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS 30.& a. The locked open isolation valves Mieras
- 31. should be given ID#'s and tagged with normal tags (Black).
- b. The valve ID#'s should be added to Mieras Done. The valve numbers are shown on Rev. 15 P&ID M-203 of the P&ID
- 32. a. Test valve 3163ES should be added to Mieras the Containment Integrity Ch~ck List
- b. Check valve 3103ES should be tagged It is not normal Palisades policy to tag with a normal tag check valves
- 33. a. The isolation valve on the sample Mieras line (3235ES) should be added to CI check list and tagged with the special CI tag
- b. This valve should be added to P&ID See comments for 17.b M.-204
- 34. None
Sheet 11 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS S Il3ILITY STATUS
- 35. a. RV 0401 is tagged RV 3342ES. This dis- Mieras crepancy should be checked and resolved
- b. Procedure for ensuring MOV's 3015 & Mieras 3016 are electrically locked closed (ELC) during normal operation should be identified
- c. Determine whether manual valves Mieras Manual valve 3205ES will be put on CI check 3190ESS, 3199ESS and 3205ES should be list (CL3.3). The other two valves will be included on CI Check List put on check list CL3.2
- 36. a. Valve line-tip ~or local leak testing Mieras should be defined
- 37. None
- 38. a. FSAR description should be revised to agree with as-built configuration
- 39. a. FSAR description should be revised to agree with as-built configuration
Sheet 12 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 40. a. The PCS sample line should be defined as penetration 40 and given a classifi-cation of Bl
- b. As noted above for penetration 21, the P&ID, Local Leak Test Procedure, Con-.
tainment Integrity Check list and FSAR should be re~ised 40a. a. The pressurizer dead weight tester Meineke According to the Reactor Engineer, this line line should be defined as penetration is no longer used and it has been capped in-40a and given the correct classifi- side and outside the containment. If the cation. line is no longer in use it should be capped at the penetration and the associated vavles, NOTE: Currently this line as a C-3 tubing and equipment should be removed classification
- b. As noted above for penetration 20, Mieras the P&ID, Local Leak Test Procedure, Containment Integrity Check list and FSAR should be revised to show the as-built configuration
- 41. None
Sheet 13 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS* SIBILITY STATUS
- 42. a. Test valve 1126PC is not tagged. This Mieras valve should be tagged
- 43. None
- 44. a. Test valves ~re being added in accor- ttarshe ance with Facility Change 446. See the Addendum at the end of Volume I for details
- 45. None
- 46. a. Test valve SOOWG is not tagged. This Mieras valve should be tagged
- 47. None 4 8. All comments, a,b,c,&d, for Penetration Mieras &
17 are applicable to this penetration Palmer
Sheet ..lJ_ of -1.!L_
TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION
- RESPON-No. ACTION ITEMS SIBILITY STATUS
- 49. a. The second valve in the test line Mieras (514 CRW) should be added to the GI Check list
- 50. a. Isolation valve P5VA was not locked. Mieras It should be.locked
- b. Procedure to check integrity of emer- Mieras gency access should be identified
- c. Emergency access door could not be Open Item opened from inside containment. The operability of this door should be checked
- 51. None
- 52. None
.. Sheet 15 of 18
- TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION
. VALVE CHECK PENE-TRATION RESP ON-No. ACTION ITEMS SIBILITY STATUS 53.& a. FSAR states there is an automatic Palmer
- 54. valve opened at SLRW tank low level and a check*valve. Check valve acts in*wrong direction for containment isolation. FSAR should be changed.
Also, automatic feature should be ..
reconsidered.
- h. These penetrations cannot be local Palmer leak tested unless the check valve
& isolation valve are reversed *
- c. Consideration should be given to Mieras These valves will be added to CI Check list adding:test valves (53-3182DRV, 54- (CLJ. 3) 3167DRW) to CI check list
- 55. None
- 56. None I
i
- 57. None
- 58. None
. Sheet 16 of 18 TABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RESPON-No. ACTION ITEMS SIBILITY STATUS
- 59. None
- 60. None
- 61. None
- 62. None
- 63. a. P&ID M-218 shows this penetration as Mieras being used for pressure instruments.
It is not. This penetration is a spare. The P&ID should be revised
- 64. None
- 65. a. Test valve 612CA is shown as 141CAS on Mieras P&ID M-212. This discrepancy should be r.esolved
- b. The test valve should be added to the Mieras CI check list
Sheet 17 of __!!!__
TABLE II-2 RESULTS OF CONTAINMENT PENETHATION AND ISOLATION VALVE cm~CK PENE-TRATION RES PON-No. ACTION ITEMS SIBILITY STATUS
- 65. c. Procedure to check integrity of pres- Mieras cont'd sure line should be identified
- 66. a. Arrangement for ILRT isolation valves Mieras The configuration will be shown on P&ID should be shown on P&ID or other con- M-218 trolled document 67.. a. CV1037 does not have a tag. It should Mieras be tagged with a normal tag (Black)
- 68. a. CV1813 *& CV1814 do not have tags. Mieras These valves should be tagged with normal tags (Black)
- 69. None
- 70. None
- 71. None
Sheet 18 of 18
'fABLE II-2 RESULTS OF CONTAINMENT PENETRATION AND ISOLATION VALVE CHECK PENE-TRATION RES PON-No. ACTION ITEMS SIBILITY STATUS
- 72. None
- 73. a. The test valve on this penetration Mieras should be given an ID# and tagged with a special color CI tag
- b. The test valve should be added to Mieras the CI check list l '
Sheet 1 of 19 TABLF. II-3 LIST OF ITEMS FON CONTAINMENT INTEGRITY CHECK.LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 1 Purge Air Supply CV1807 Control Valve Normally Closed CV1808 Control Valve Normally Closed 508VA Manual Test Valve Locked Closed
Test Connection Capped 2 Main Stearn Line CV0510 MSIV Nor.rnally Op'en (SGE50A) llOMS Manual MSIV Bypass Normally Closed This valv.e is to Valve be replaced by mo-tor operated valve MOV 0510A. (see FC445-l) 3 Main Stearn Line CV0501 MSIV Normally Open (SGESOB) lllMS Manual MSIV Bypass. Normally Closed This valve is to Valve be replaced by mo-tor operated valve MOV 0501A (see FC445-2) 4 Purge Air Exhaust CV1803 Control Valve Normally Closed CV1805 Co.ntrol Valve Normally Closed CV1806 Control Valve Normally Closed 506VA Manual Test Valve Locked Closed
Test Connection capped
Sheet 2 of _l.L TABLF. II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 4a Purge Air Exhaust lOOVAS Manual Isolation Locked Closed :
Valve Sample Line lOlVAS Manual Isolation Locked Closed Valve 507VA Manual Test Valve Locked *closed
Test Connection Capped 5 SG (E50A) CV0767 Control Valve Normally Closed Bottom Blow CV0771 Control Valve Normally Closed 567MS Manual Test Valve Locked Closed
Test Connection Capped 6 SG (E50B) CV0768 Control Valve Normally Closed Bottom Blow CV0770 Control Valve Normally Closed 568MS Manual Test Valve Locked Closed
Tes\: Connection Capped 7 Feedwater to SG 746FW Manual Drain Valve Locked Closed (E50A) 746AFW Manual Drain Valve Locked Closed
Drain Connection Capped 8 Feedwater to SG 747FW Manual Drain Valve Locked Closed (E50B) 747AFW Manual Drain Valve Locked Closed
Drain Connection Capped
Sheet ~3~- of -12__
TABLE II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICA'fION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 9 Spare :
10 Service Air .122CAS Manual Isolation Locked Closed Valve 142CA Test Valve Locked Closed
Test Connection Capped 263 Check Valve Closed 11 Condensate to CV0936 Control Valve Normally Open Shield Cooling Tank 536CD Test Valve Locked Closed 536ACD Test Valve Locked Closed
Te.st Connection Capped 223 Check Valve Open 12 Service Water Supply The service water 13 Service Water Return
) system is not with-in the scope of the containment integ-rity check list.
14 Component Cooling CV0910 Control Valve Normally Open 507CC Manual Test Valve Locked Closed
Test Connection Capped Open 0910CC Check Valve
---~
Sheet _4__ of 19 TABLE II LIST OF ITEMS FON CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 15 Component Cooling CV0911 control Valve; Normally Open :
Water Out CV0940 Control Valve Normally Open 508CC Manual Test _Valve Locked Closed
Test Connection* Capped
Test Connection Capped 16 SG (ESOA) Surface CV0739 Control Valve Normally Closed*
Blow Down 17 Containment Pres- PS1802 Pressure Switch Installed sure Instrumentatib1 ----- Isolation Valve Locked Open for PS1802 PS1802A Pressure Switch Installed
. I'solation Valve Locked Open for PS1802A
-PS1804 Pressure Switch Installed
Isolation valve Locked Open
- for PS1804 PS-1804A Pressure switch Installed
Isolation Valve Locked Open for PS1804A PT1812 Pressure Trans- Installed-mitter
. ----- Isolation Valve Normally Open for PT1812
Sheet 5 of 19 TABLE II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 17 PT1815 Pressure Trans- Installed :
contd mitter
Isolation Valve Normally Open for PT1815 18 Fuel Transfer *rube ----- 4" Flange Blanked Off
36" Flange Blanked Off
36" Manual Valve Normally Closed 19 Personnel Lock Outer Door P5A Manual Test Valve Locked Closed
Pressure Tube Pressure Gauge Installed
Pressure Tube - Capped
Equalizing Valve Normally Closed Inner Door ----- Pressure Tube Capped
Pressure Tube Capped
Equalizing Valve Normally Clo~ed 20 Spare 21 Capped Spare ----- Pipe End (Inside Capped Coritainmen t)
Sheet __6_ of _u_
TABLE II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMEN'l'S 21 ----- Pipe End (Outside Capped :
contd Containment):
22 Redundant High Pressure The high pressure Safety Injection safety inspection
)
system is not with-in the scope of thE 23 High Pressure containment in-Safety Injection tegrity check list.
24 Spare 25 Clean Waste CV1064 Control Valve Normally Open CV1065 Control Valve Normally Open 512CR Manual Test Valve Locked Closed
Test Connection Capped
Drain Connection Capped PT1065 Pressure Trans- Installed mitter 647CRW Isolation Valve Normally Open for PT1065
Sheet _7_ of 19 TABLE II-3 LIST OF ITEMS FOF CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 26 Nitrogen to Ouench CV1858 Control Valve , Normally Closed :
Tank 581N2 Manual Test V~lve Locked Closed Test Connection Capped 223 Check Valve Closed.
27 ILRT Fill Line Inside Containment ----- Pipe Plange Blanked Off Outside Containment MOV-Pl Motor Operated Iso- Normally Closed
~
lation Valve 604VA Manual Isolation Locked Closed valve 605VA Manual Isolation Locked Closed Valve
Test Connection Capped 28 Containment Air Sample Line Inside Containment SV202-P Solenoid Valve Normally Closed SV202-M Solenoid Valve Normally Closed SV202-N 'Solenoid Valve Normally Closed Outside Containment ----- Pipe End Capped
Pipe End Capped This penetration will be capped out-side containment per SFC 79-094.
Sheet ~8~- of 19 TABLE II-3.
LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 29 Capped Spare Inside Containment Pipe Flange Blanked Off Outside Containment Pipe End Capped 30 Containment Spray CV3001 Control Valve Normally Closed Isolation valve 3227ES Manual Isolation Locked Closed 3258ES, which
- valve should be locked 3344ES Manual Test Valve Locked Closed open, is not with-
- rest Connection Capped in the scope of the containment integrity check list.
31 Containment Spray CV3002 Control Valve Normally Closed Isolation valve Pump Discharge 3217ES Manual Isolation Locked Closed 3259ES, which Valve should be locked 3346ES Manual Test Valve Locked*Closed open, is not with-
'l'es t Connection Capped in the scope of the containment integrity check list.
Sheet 9 of 19 TABLF. II-3 LIST OF ITP.MS PDF CON'fAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 32 Low Pressure 3163ES Manual Isolatio,n Locked Closed The other valves Safety Injection Valve associated with this penetration are not within the scope of the con-tainment integrity check list.
33 Safety Injection 3234ES Manual Isolation Locked Closed Tank Drain Valve 3235ES Manual Sample Line Locked Closed
- Valve 3236ES Manual Isolation Locked Closed Valve 3237ES Manual Isolation Locked Closed Valve 3348ES Manual Test Valve Locked Closed
Test Connection Capped
Sample Line Capped Connection 34 Spare
Sheet 10 of 19 TABLF. II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER
- DESCRIPTION NORMAL OPERATION COMMENTS 35 Shutdown Cooling MOV3015ES Motor Operated , Electrically Other manual valvef Return Valve Locked Closed are covered by MOV3016ES Motor Operated Electrically Engineered Safe-Valve Locked Closed guards Valve Check RV0401 Relief Valve Normally Closed List.
RV3164 Relief Valve Normally Closed 3204ES Manual Sample Line Locked Closed Valve Sample Connection Capped 3205ES Manual Isolation Locked Closed Valve Pipe Flange Blanked Off 36 Letdown to Purif i- CV2009 Control Valve Normally Open cation Ion Ex- 2320CVC Manual Test Valve Locked Closed changer Test Connection Capped 37 Primary System CVlOOl Control. Valve Normally Closed 503CRW Manual Test Valve Locked Closed Check Valve Closed Test Connection Capped
Sheet _ l l _ of _n_
TABLF. II-3 LIST OF ITEMS FOR CONTAINMENT INTP.GRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 38 Condensate Return CV1501 Control Valve Normally Closed From Steam Heat- CV1502 Control Valve : Normally Closed ing Units 502VA Manual Test Valve Locked Closed
Test Connection Capped 39 Containment Heat- CV1503 Control Valve Normally Closed ing System 503VA Manual Test Valve Locked Closed
Test Connection Capped
Pipe Flange Blanked Off 40 PRC Sample Line CV1910 Control Valve Normally Open CV1911 Control Valve Normally Open ll 70A Manual Test Valve Locked Closed 1170B Manual Test Valve Locked Closed Test Connection Capped 40a PZR Dead Weight CV0120 Control Valve Normally Closed Tester CV0121 Control Valve Normally Closed 1129PC Manual Test Valve Locked Closed
'fest Connection Capped 41 Degassif ier Pump CV1004 Control Valve Normally Open Discharge 506CRW Manual Test Valve Locked Closed
Test Connection Capped
Sheet 12 of 19 TABLF. Il'.""3 LIST OF ITEMS FOR CONTAINMENT INTF.GRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 41 ----- Check Valve ' Open contd 42 Demineralized CV0155 Control .Valve Normally Closed
.Water to Quench 1126PC Manual Test Valve Locked Closed Tank ----- Test Connection Capped
Check Valve Closed 43 Spare 44 Controlled Bleed CV2083 Control Valve Normally Open Manual test valve Off From RCP's 2083 Manual Test Valve Locked Closed 2083Ais to be 2083A Manual Test Valve Locked Closed added per SF
Test Connection Capped 45 Charging Pump CV2111 Control Valve Normall,y Open Discharge 2110 Check Valve Open 46 Containment Vent CV1101 Control. Valve Normally Open Header CV1102 Control Valve Normally Open SOOWG Manual Test Valve Locked Closed
Test Connection Capped
Sheet 13 of 19 TABLF. II-3 LIST OF ITEMS FOF CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 47 Primary System CV1002 Control Valve Normally Open Drain Tank Pump CV1007 Control Valve : Normally Open Suction 502CRW Manual Test Valve Locked Closed
Test Connection Capped 48 Containment Pres~ PS1801 Pressure Switch Installed*
sure Instrumenta- ----- Isolation Valve for Locked Open ti on PSlBOl PS1801A Pressure Switch Installed
Isolation Valve for PS1801A Locked Open PS1803 Pressure Switch Installed
Isolation Valve for; Locked Open PS1803 PS1803A Pressure Switch Installed
Isolation Valve for Locked Open PS1803A PT1805 Pressure Trans- Installed mitter
Isolation Valve for Normally Open PT1805 P'l'l814 Pressure Trans- Installed mitter
Isolation Valve for Normally Open PT1814
Sheet 14 of 19 TABLF. II-3 LIST OF ITEMS FOR CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 49 Clean Waste CV1036 Control Valve Normally Open Receiver Tank Circ CV1038 Control Valve Normally Open Pump Suction 513CRW Manual Test Valve Locked Closed Test Connection Capped 514CRW Manual Drain Locked Closed Valve 50 Emergency Access*
Inside Containment Pressure Equali- Normally Closed zing Valve Pressure Tube Capped Pressure Tube Capped Outside Contain- Pressure Equali- Normally Closed ment zing Valve Pressure Tube Pressure Gauge Installed Pressure Tube Capped P6VA Manual Test Valve Locked Closed Test Connection Capped 0-Ring Test Con- Capped nection 51 Equipment Door 0-Fing Test Con- Capped
-nection
Sheet~ of. 19 TABLF. . II.-3 LIST OF ITP.MS FOF CONTAINMENT INTEGRITY CHECK *LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 52 Containment Pump CV1103 Control Valve Normally Closed Drain to Pump. CV1104 Control Valve : Normally Closed Tank 500DRW Manual Test Valve Locked Closed
Test-Connection Capped 53 Containment Spray CV3029 Control Valve Normally elosed Pump Suction 3182ES Manual Test Valve Locked Closed 3181 Check Valve Closed
Test Connection Capped 54 Containment Spray CV3030 Control Valve Normally Closed Pump Suction 3167ES Manual Test Valve Locked Closed 2166 Check Valve Closed
Test *connection Capped 55 SG (E50B) Surface CV0738 Control Valve Normally Open Blowdown 56 Spare 57 Spare
Sheet 16 of 19 TABLF. II-3 LIST OF ITEMS FO'F CONTAINMENT IN'l'F.GRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO, SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 58 Spare 59 Spare 60 Spare 61 Spare 62 Spare 63 Spare 64 Reactor Cavity 120SFP Manual Isolation Locked Closed Fill and Recirc Valve 121SFP Manual Isolation Locked Closed Valve 514SFP Manual Test Valve Locked Closed
Test Connection Capped
Sheet 17 of. 19 TABLF..II-3 LIST OF ITEMS FON CONTAINMENT INTEGRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 65 Instrument Air CV12ll Control Valve , Normally Open 612CA Manual Test Val've Locked Closed 263 Check Valve Open PS1220 Pressure Switch Installed 6llCA~ Isolation Valve for Normally *open PS1220 Test Connection . Capped -*
66 ILRT Instrument 601VA Manual Isolation Locked Closed.*
- Line Valve
- 602VA Manual Test Valve Locked Closed 603VA Ma:nual Test Valve Locked Closed L6 Man~~l Isolation Locked Closed
. Valve Test Connection Capped Test Connection Capped 67 Clean Waste CV1037 . Control Valve Normally Open Receiver Tank Pump 515CRW Manual Test Valve Locked Closed-
. Recirc Test Connection Capped Check Valve Open
Sheet 18 of 19 TABLF. II-3 LIST OF ITEMS FO:F CONTAINMENT IN'fF:GRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 68 Air Supply to Air CV1813 Control Valve Normally Closed Room CV1814 Control Valve : Normally Closed 505VA Manual Test Valve Locked Closed
Test Connection Capped 69 Clean Waste CV1044 Control Valve Normally 0pen Receiver Tank Pump CV1045 Control Valve Normally Open Suction 518CRW Manual Test Valve Locked Closed
Test Connection Capped 70 Spare 71 Spare 72 Reactor Refueling 117SFP Manual Isolation Locked Closed Cavity Drain Valve 118SFP Manual Isolation Locked Closed Valve 515SFP Manual Test Valve Locked Closed
Test Connection Capped
Sheet 19 of 19 TABLF. II-3 LIST OF ITEMS FOF CONTAINMENT INTF.GRITY CHECK LIST PENE-TRATION IDENTIFICATION CONDITION DURING NO. SYSTEM NUMBER DESCRIPTION NORMAL OPERATION COMMENTS 73 Capped Spare ----- Pipe Flange ( In;:;idE Blanked Off Containment)
Pipe End Capped 509VAS Manual Test Valve Locked Closed
Test Connection Capped
MPR ASSOCIATES. INC.
III. APPENDIX
PALISADES NUCLEAR PLANT Procedure for Locating and Identifying Containment Mechanical Penetrations and Isolation Valves Procedure No. MPR-98-56-1 Rev. O 10/11/79
RECORD OF REVISIONS Rev. Affected No. Description of Changes Date Pages 0 Original Issue 10/11/79 MPR-98-56-1 Rev. O, 10/11/79 i
l_*
PALISADES NUCLEAR PLANT PROCEDURE FOR LOCATING AND
. IDENTIFYING CONTAINMENT MECHANICAL PENETRATIONS AND ISOLATION VALVES (MPR-98-56-1) 1.0 PURPOSE The pur~ose of this procedure is* *to define the steps
- to be taken to (1) *check the *configuration of all. contain-ment mechanical penetrations. which requir~ isolation after postulated accidents and.associated isolation valves and (2) ensure that.the applicable documents as listed.in Attachment l, confirm to the as-built con-figuration.*
2.o* REFERENCES See Attachment.l for list of* drawings and other references.*.
3.0 PREREQUISITES 3.1 Radiation protection.requirements have been determined for personnel performing work a]1.d Radiation Work .Permit (RWP) has been obtained from Rad. Pro.
3.2 Access. to th~ inside.and outside of the containment building is required.
3.3 The master list (Table 1) mechanical p~ne-trations and isolati,on valves has been prepared using the referenced documents.
MPR-98-56-1
- Rev. O, 10/11/79 I_
'f 4.0 PRECAUTIONS AND .LIMITATIONS 4.1 Contamination.and radiation will be present for some of this work. Radiation protection require-
- ments must be.determined prior to starting any work.
s.o* PROCEDURE 5.1 Physically locate each containment penetration which requires isolation after postulated accidents and associated isolation valves on the master list (Table 1) and place a temporary identifying mark. Whenever possible, take a photograph of each penetration both inside and outs*ide the containment. Note the picture number in the appropriate column of Table. 1.
5.2 Based on this inspection make corrections and changes on the master check list so that the configuration on the master list conforms with the as-built conditions.
5.3 Visually _check all mechanical penetrations which require isolation* after postulated accidents and associated isolation valves* to ensure that each one has. been accounted for.
5.4 Check the referenced documents (Attachment 1) against the master list (Table 1) and note any corrections or changes which are required to bring* the referenced documents into conformance.
MPR-98-56-1 Rev. 0, 10/11/79
5.5 Prepare a list of all containment penetration automatic and manual valves which should be closed during*normal operation. The purpose of this list is to permit Palisades plant personnel to place a tag on each one of these valves noting that the valve should be closed during normal operation.
- MPR-98-56-1 Rev. O, 10/11/79
ATTACHMENT l LIST OF REFERENCES
- 1. Palisades FSAR Table 5.2 (Rev. 09/14/79), "Containment Penetrations and Valves*." *
- 2. Palisades- Procedure R0-32, Table 1 (Rev. 09/04/78), "Local Leak Test Results."*
3.. Palisades "Contairunent Integrity Check. List (Rev. 3)."
- 4. Bechtel P&ID's for Palisades:
M-201 (Rev. 18) Primary Coolant System M-202 (Rev. 19) Chemical and Volume Control System M-203 (Rev. 16) Safety Injection, Containment Spray and Shutdown Cooling System M-204 .. (*Rev. 16) Safety Injection, Containment Spray and Shutdown Cooling System M-207 (Rev. 31) Feedwater and.Condensate System M-208 (Rev. 19) Service Water System M-209 (Rev. 19) Component Cooling System M-210 (Rev. 14) Radioactive Waste Treatment System, Clean M-211 (Rev. 26) Radioactive Waste Treatment System,
.Dirty Waste & Gaseous Waste M-212 (Rev. 9) Service and Instrument Air Systems.
M-215 (Rev. 14) Plant Heating System
- M-218 (Rev. 18) Heating, Ventilation and Air Conditioning M-219 (Rev~ 10) Process Sampling System M-221 (Rev~ 9) Spent Fuel Pool Cooling and Shield Systems ..
M-222 (Rev. 9) Miscellaneous Gas Supply Systems
- 5. Bechtel Construction Drawings M-140 (Rev. 4) Penetrations - Containment Buildi~g Wall MPR-98-56-1 Rev. O, 10/11/79
!MIL[ 1 M*'211.!UJ~U~U~~!. ~ii.QI:~
CONT,, rn~H ~H ~I CllMll Uil f'l :a rRM l or:s SllEET __ I _OF _ _
f'LNL- l.OCi\ 1r:n rriSf'[CTED I
mAT!ON CONF lGURAT ION P& ID MID PllO 10c;r.r.r11rn NUMBER SYSTEM
~:u;*iBLR M~~I'- OUTSIDE COiHA!NME.Nf I NS IDE cotn rnmrn OUTS lDE lilS [CE CLA "'
NC NC.
~ ~ S<?~
?URGE AIR I
~vi;~~ he=-
M*218 SUPPLY 1808 1807
.L.Ct*-soevA (Al)
MAIN STEAM t...HJ=: FROt-1 STE.AM Gc.N:;;.~...A.10!'! A MAIN STE:AM z FOR DETAILS s-- J M*207 LINE FIGURE A-I (er)
MAIN STEAM LINE. !=~OM STE'AM GENERATOR 'O MAllJ STEAi.ii s FOR .:STAJL.S sc:-
-c. ] M*C'07 LINE' FIGURE A*Z (c.1)
~NC
- ~rt CYl603
~NC
\
4 4~
Iii"' ~*'"""""'
.cv 1805 cv1eoc.
T 5~
. sz" 48" M-218 PURGE EXHAUST AIR
/ LC ~"l-IZ,..,ZOR
'/z"- 501 A (Al)
MPR-98-56-1 Rev. O, 10/11/79 1_*
Tfllll.E l.
M1is f[.R 11:; r nr r,'\1 l_'.:~:~r_s_
' CONTfllrlMINI MlLll!irllrnL l't ~a! l\f\f 1mis SllffT _z_ OF-'--
PUlE- LOCATUl, lr_;Sl't.Cl LD TRAT!ON . CONFIGURATION
- P& ID AND PllOTOGF:i\PllLD NUMHE.R tlUMBFR SYSTEM Arm OUTSIDE corlTAirlMENT INS i DE CONT AltmENT OUTSIDE !US(()[
CLASS *'
NC. .
-~ T/'~:~7,MS CV 0771 t I !P.
CV ., 12* M*207 SG. (ESOA) s 07G7
- ~ M*?ZG BOTiOM SLOW (CZ)
NC
~v
-~
t 1>*-~~BM* .
0770 ~
G 07(08 CV 't 1z" M*207 SC:. ( E 50 s)
I~ M*lU. BOTTOM BL.OW (cz)
~t*N2l6R*0704
~ ......L . . . -
6" 1S'!N218R
- 070e 7 I -
,.ao* M*Z07 FEE DWA"TER TO
~
IS" J 1a* SGt ( E 'SOA)
(CJ)
G"*N218R*0703 i:;.*
8 1a'~NZ18~*0701 I
.,30*
M*Z0.7
- 16" J 18" (ci)
MPR-98-56-1
- Rev *. 'o, 10/11/79
TM'U l Miis.LIT._ Lt~r_:u~lJ.'.~.~n-~
com II Irl:-11 ~If M! Cl!l1W ,\[ f'frH Ii\;\f Iur:s SllFET _s_ OF _ _
PUI[- l.O\J\ILD. l ~1:.if'll TI J TR"1 ION CONFIC:URJ\f IOtl P& I [1 111m rH:JTOGRl\f'fi[D NUMB LR NUi*il\lR SYSTEM
/IND CLASS OUTS IDE com II Iil~1ENT INSIDE ClliH:'\lfi~\ENf OUTSIDE ms 1uc 12*
'I J r
l
- SPARE (N/A)
/0 2~i:'c.3 I
2!1zzcAs
~
,...-L.C."'
r l
1z
z" M*21Z SERVICE AIR i..c: :14-Z CA T
(Ae)
NO
~
1Y{-2zs 1z* CONOENSAi"E 1'0 II I J 1 1Yi' M*221 SH\C.LD COOLING
.... ~ ~
I CV SURGE TAN~
oqsq
- ~ */'!. s;,aco T
(ce)
MPR-98-56-1 Rev. 0, 10/11/79
!Mil [ I M,,~JJB...l.!.'..:.ULl'.!'!Ll.'.::'Df~
. CO~H AIrl:!i :u
!11 M! LIWI If.AI f'f ! Riif to~:S
- SHEET 4 OF PUil.- LOCA l Lil, I NSflJ l [!.'
TRAT ION CONF IGlJR,\ 11 ON* P&!D MIO r11u !OliR;\f'lif.D tlUMllLR 1-------,_..;..~---.-------------.l m:~HER SYSTHI.
Arm pUTSIDE CONT1\1:mrn INSIDE CONTAiriMENT OUTSWE WSI:JE CLASS 10*
,)
12"
. :: s* 1--l~
IC.
- ~*:;:LJ~IG::."
~. _ eo"
__.1,;---
1
- l CV OSGS M*ZOS SERVIC~ WATS.I:
SUPPL'(
. I/
I~
10' _ a* 1~~
c:v 06'70 (x)
~.,!-
- - - i... -a CV 0843 *
.--o.-s"..; a"'---,
1-"
~ *~~ I 21>! CVOSG7 410 10'
.~*
CVOBG?.
=
1e"
@i.
10" g"
- A . '-1.._ I .
- ~.r-~ .r-~
- jE . <::?.>' C:VOS.04 M*eoa SCR'VICE; WATE.~
13 ., ~ . oes4 I~ 408 . RE."TUet-J Q ~. I IG" L -~:-
CV ose<£ 20*µ c:voasa I) 10" s**, ...
- .r ---i'l.f-- -
a* cv oa~r 1a* ~~~
1)
-~
~v
.osn:. ~
ro*'
(X)
MPR-98-56-1 Rev. 0, 10/11/79
fl\P.LE l Mi\TI!*JLU~'L~!~~:*:~L~-
COllT AIfi:'!rn I l~[C llMI ICM f'I ~if l fi,'1 r IilrlS SHEET _s_ OF __
PENE- LOCATl.D. I~SPlCTEJ TRATION CONFIGURAT!Qrl P& Ill . f\llD f'llOTO~:R/l!'tiED NUMB FR SYSTEM
~------.....;----,.....------------t flUMBER AND OUTS IDE CONT AIrlMENT !NS IDE- CONT/\ lrtMENT OUTSIDE .lHSl~E CLASS NO
. 14 1-i I 1o~lS7* oq1occ
~
cvoq~
1.. *
~ M*eO'l COMPONENT
. COOLING IN WATER'
. ti~*ro7CC t.C
- T (cz).
NO NO 15 r-1il CV 0'140 i-.
~~
CV~"
~o" M*20<:!
COMPONENT COOL.ING. WA~R OUT LC *~s07CC (c2)
__.t .. 073,
,, -, r 1 ~* 2*
I lvt-207 SG (:so A)
SIJZFAC!: 13l.OW oowt.J (Cl) 90p9 ~} . l'X'Z ISIZ I?"
CONTAl/.JMENT 17 l.lOT 5PECIFIE.D ( ~ . Yz~ M-e1a PRE.SS URE' 11-lSTRUMEIVT-ATIOl.J 1ai4 1e1s (NOT G1vE.N)
MPR-98-56-1 Rev. O, 10/11/79 I~
.' I fllll.l l Mll~lU!~.L!.L!]L!~J~J1[~
CONT/\ Jrt:*li ~It MLCllMllCM. f'UH 11{/\ I 1or1s SHEET _9_or _ _
PEN~. - LOCi\fEl, UISf'ECHD TRflTiDN CONF IGU Rf\ Tl ON P&!D ANO PHOTOr.RAPllED NUMBER NUMBER SYSTEM Mm CLASS OUTSIDE corlT/\n::mn !llSIDE chNTA!fl~1ENT OUTSIDE ms IDE ro Pi:Ne-.
".33 ..Le~
~
3zz7es I -
.....~~~
CONTAINM<;NT L.O 12*
so. e' 9"_ M*Z03 SF'RA'!' PUMF'
~ ......' ............. J CV3001 DISC.l-fARGe:
LC~ :./'!33<\4ES.
T ..
(X)
!TO Pi1'11!.
4'33 .*~c. ~
3Zl7ES
~
- CONTA INl.;IENT 31 8"1'-J- ~O*.
....~~ ~*' ,rz." 8" M*Z03 SF'R~Y P'.Jv.?
i--t -v--.. J CV*3002. OISCHAR6e
\.C: ~ :1*~3~4-(;ES "I
(x)
..p-.. M0.*3008
~
~ ***~.*
. .P.1.140-SOIO .
~:: -~
3-C ,
I r 1"* r?.." - M-Z0:3 L...P. SAFETY v"><,
CV300~
~ 111 1J QM0*301Z M-ZO"- IN..JE'CTJOl'J
('/.)
tf' a
30
. " ~,
.. "'~
.H
'TO pe1Je"
""35
~
QM0*3014 .
~ , I FROM PENS.
~30 r--
L.C~
~J!'.;?.3C.ES SAFcT'(
1?"' ,,
, z
~
L.C:
M*Z04 INJEC.T I 0"-1 33 i:'-32.311:;.S.
>.:.H J
- e'Jil4ES
- iA"-1\:. CRAIN l'li!OIAPEwe. I LC.~ ~3S48ES
".31 r--
(C3)
MPF.-98-56-1 Rev. Oj 10/11/79
11"1!11 L 1 M,~s ff,_~U~~.AL!IN!f~.
com I\ 1rm1 a1 ME rn:.r: 1c,;t_ l'f ~H 1Rr1r11ms SllEET _JQ__ OF_..
PGlE- LOCAi! D, rnsri::rn.::i TRl\TION CONF IGURI\ l lON P&IO SYSTEM ANO f'llOTOGRAPlffD llUMllE.R NUMBER A!IO .
CLJ\SS OUTS lDE CO!H i\ ir:rmlT . INSIDE CONTi\Ill~*~ENT OUTSIDE ms IDE 34 18' 11 . .- SPAE.E (N/A)
.I-2V31G~
L.C
- ~
)
- ..a*.3z05
~-
14'*31qo ' 1¥2' ~M~ ~MO
-. Z.4-' .3lS 31~
SHUTDOWU
.35 ,.,14' " ' !2" iJ ~ M-W4 COOLING RETURN
~~,,
,._t.C...,
,. evo.;cl 14*.31q"*
FE0"1 PE~E. ".3Z (82) 3(0 1
- r "c~;iZ
.... .A Z'.<,I~~
. ...2.,..~L
- .T 2010 I . . .. .-,IZ' I II,"
cv zooq Li .
Q s . 1,;1-2oe LEIOOWV pueJFICATJOIJ 10'-'
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- xc HA1'JGce
- ~
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C:V:ZIZ.1.
- z*.z.14qA
~Pt..* ....
....,.._, ct L.C ~l'Z3ZO eve (131)
. ~
PRIMAl?y SYSTEM
~7
!,'2." IY~" . M*ZIO PUMP .
~ 02Al1'J .
"' * ~v 1001 J
eec1ec:.
LC: ~1'!503ci:w -
(cz>
MPR-98-56-1
.Rev. 0, 10/11/79
llil'ol.t l M1\~ll R l IST_!_l[_l','!J s:.n1j_
corn I'd r::*1Ull Ml (llj,~l{ L\l !'~ ~:u RM (()~IS SllEET _r_r_OF __
!'Ull - LOCM lll, I~.;)!'ECil:
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U'-llT.S r...c:. ~:c..soz. VA (X)
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MPR-98-56-1 Rev. O, 10/11/79 l_
lilflE l Ml\Sj_!JLL!~Ulf" P1~!J~rr~ ~
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. PUI£- LOC1iTLD. !tiSP[Cf[D TRAT !011 CO!IF IGURA l IOil P&!O SYSTEM AND f'llrJTOG\APllED NUMilf.R NUMBER
. ArlD OUTSIDE corH.~lllMENT INSIDE CONTAIN~ENT OUTSIDE INS !DE CLASS.
~
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MPR-98-56-1 Rev. o, 10/11/79
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- t'
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(cz)
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<!.VI0'38 CY 103 ..
SUC.TIOr.J
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MPR-98-56-1 Rev. O, 10/11/79
TABLE 1 MASHR l IST OF f'i\l.fS;i[lfS COrlTAIN~LNT M(C!IMllCAL f'DlURflrlONS _
SHEET ~OF _ _ .
PENE- LOC1\TUI, IN:iPECltD TRATION CONF IGURAT IOll- P-& ID SYSTE.'1. ;\ND f'HOTOGi:Ai'HlD NUMBER NUMBER
- AND CLASS OUTS IDE CO~H A!rlMENT INSIDE CONTAINMENT OUTSIDE *ms IDE 5!.10" 50 L,f 1&,f?. - 5ME'RGE1'1C'I
ACC:.ES.S (x) 12~0*
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(x)
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241'3181
~
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T (x)
MPR-98-56-1 Rev'. 0, 10/11/79
. TABLE l M.l\Sf[ R I l~T or f'M 1:..i_OJi corn AIN:lf.~IT MfCll/1~11!;\L f'UH [R;\f IOllS SHEET ...!§__ OF_._.*
Pf.NE- LOCAIEO,. !HSPECTlD TRAT ION CONFIGURATION .* P& l D AND PfitlTOG:\ArllED SYSTEM*
.uru ct::~s i----0-UT_S_ID_E_C_O_NT_A_Ir-IM_EN_T_ _.,....._ _! N_S_IO_E_C_O_N_TA-lf-li1_EN_T_ _-4
.~~
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M*22' 13LOWDOW1'l (Cl) 1e" sc. I J SPAeS:
(1J/,i..)
s; MPR-98-SG-l
- Rev. O, 10/11/79
TABLE 1 MASHJLl !ST llf'. f'llL!l.0.P!i cormrn1:*1Ull ~fm\rl!C\L l'HH IR/\T IONS SHEET ...1L OF _ _
PEtlE- LOCATED, INSPECTED TRAT ION CONFIGURATION P&ID SYSTEM
- AND PllOTOGRAPflFD
- NUMBER NUMBER AND CLASS OUTSIDE CO:lTl\!rl,'lENT- INSIDE COflTAW;mn OUTSIDE ms IDE 58 I
12*
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rz"
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MPR-98-56-1 Rev. 0, 10/11/79
TAlll.E l
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CONTAIN~mir M[CllMI IC,~L f'UIURM 1ur1s SHEET -1!._. OF _ _*
PCNE- LOCA![O, lNSPEClLr
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![
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PEllE- LOCAf[U, INSPlCl~~
TRATION CONFIGURATION P&ID AND f'llUTOGRAf'llED SYSTEM NUMBER Arm 1------------r--------------; NU;.\BER OUTSIDE CONTAINi*lENT INSIDE CONTA1mmH OUTS IDE INS IDE CLASS
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(x)
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TABLl l MllS fl R LI ST llF Pl\J.l::.~nr1 CONTI\ rn:1t rn MfO!Ml!C/\l. f'Hl[ rRAT 10:1s SllEET _LS_ OF_l_q_ .*
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MP R ASSOCIATES.* INC.
ADDENDUM l to Report MPR-693, "Palisades Nuclear Plant -
Independent Review of Containment Penetrations"
Table l of this addendum presents the new configuration of several penetrations which have been or will be modified since the initial inspections were performed on October 15-17 and 23-24, 1979~ When these modifications are implemented, the master list (Table II-1) and the reference documents should be updated to be consistent with the as-built configurations.
T1iBLE 1 OF ;iOnrnouM SLirlMARY or (11,W*l-t: l~I f'P()CR[SS OF AS-~U I LT CD:IF IGUf\M [Oil ,1F PF~lE TRAT ION LINES AND VALVES AFFECWlG
- CO~Hi'\!NMENT ISOLATION SHEET ._1_ OF_Z_
PENE*
TRAT ION CONFIGURATION P&IO NUMBER . SYSTEM COMMENTS NUMBER AND OUTSIDE CONTAINMENT INSIDE CONTAINMENT .
CLASS MA.NUA.L. B'IPA.S':i NO
~ RELIEI=~
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T1\BLE l OF 1iDDENOUM
SUMMARY
OF CllMHif) I ~l rr.rriRr.ss OF
. *AS-BUILT COilr!GllflAT!C;: JF PCIETRAT!ON LINES AND VALVES AFFECTING CONTAINMHH !SOLMION SHEET 2 OF z PENE-.
TRATION CONFIGURATION P&ID COMMENTS NUMBER SYSTEM NUMBER AND OUTSIDE CONTAINMENT !NS IDE CONTAINMENT CLASS 10* - a*~
"MO I MOCIFIC ...."TIOM
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~ ----- -
Exhibit 2 PALISADES MANAGEMENT REVIEW TASK FORCE PROGRAM PLAN Revision 2 November 28, 1979 I. Introduction Quality Assurance Program. Procedure 1-52 requires the preparation of a written plan to identify personnel, assign responsibilities and establish lines of communication as part of a task force formation. This Program.
Plan fulfills that function for the Palisades Management *Review Task Force (PMR'I'F).
II. Task Force Objectives The objectives of the PMRTF are to organize and direct the actions to be taken by Consumers Power Company as required by the modification to the Palisades Plant operating license (License No DPR-20), dated November 9, 1979. The Task Force was originated to accomplish these activities in a coordinated fashion and on a schedule consistent with plant startup.
Specific requirements are:
A. Conduct a comprehensive review of all procedures and checklists prior to startup following the present refueling to assure that:
(1) all valves and other controls for engineered safety features have been identified in such procedures and checklists; (2) such procedures and checklists require that all such valves and other controls are in their proper position prior to startup after any cold shutdown; and (3) such procedures and checklists require that after testing, maintenance or other activities which involve manipulating such valves and other controls, the valves and other controls have been returned to their proper position for operation.
B. Prepare procedures for:
(1) inspecting all accessible valves and other controls for engineered safety systems for compliance with the Limiting Condition for Operation (LCO) requirements of the Technical Specifications at least monthly during operation, and (2) reporting the results of B(l) to the Director of the NRC's Region III office.
C. Prepare information for presentation to the Director, NRC Office of Inspection and Enforcement prior to startup following the present refueling which explains how the requirements of the November 9, 1979 modifications to License No. DPR-21 will be implemented.
2.
III. Task Force Organization In order to accomplish the PMRTF objectives, four action sequences must be completed. They are:
- 1. Review applicable checklists and procedures and correct deficiencies.
- 2. Review Technical Specifications Section 3 to identify monthly procedures for use during operations. Develop new ones if needed.
- 3. Develop an equipment/limiting condition of operation matrix to strengthen the equipment outage request processing done for many maintenance procedures.
- 4. Develop both written and oral responses to the NRC letter.
The steps necessary to accomplish each action are displayed in flow charts numbered "FC-1" through "FC-4", which also identify team responsibility for each step.
To accomplish these action sequences, the PMRTF has been formed with a Task Force Manager, a Task Force Coordinator, and five working teams, each with a Team Leader (See Appendix A). Each team is assigned the specific responsi-oilities shown in Appendix B.
Team Leaders are responsible for developing the procedures identified in Appendix C. Team Leaders also establish personnel qualifications requirements for their team. The Task Force Coordinator reviews team procedures and personnel qualification requirements, documents personnel qualifications, and secures personnel as needed.
- IV. Records of Activities A. PMRTF Meetings: A resume of all PMRTF meetings will be prepared by .the Task F_orce Coordinator and distributed to members of the Task Force, the Executive Vice President - Energy Supply, and to Document Control.
B. All Task Force correspondence will be permanently filed under the following Uniform File Index numbers:
950*40*01 X950*71*01*05 X950*02200 C. All reviews will be documented and will be signed by the reviewers.
V. Reporting A. Routine: The Task Force Coordinator is responsible for preparing a written report for the Task Force Manager each seven days commencing Wednesday, November 21, 1979. This status report will include:
(1) Brief discussion of significant problems, proposed resolution and their schedule impact; (2) Recap of the past week's activities;
3.
(3) Brief description of plan for the following week; (4) Number and source of personnel involved, including contractors, and (5) Current overall schedule.
B. NRC Reporting: The Task Force Manager is responsible for preparation of the 20 day response to the NRC and subsequent reporting. Routine contacts with NRC Region III will be the responsibility of the Palisades Plant Staff.
VI. Follow-up Mechanisms A. Short-term: All discrepancies which require resolution prior to nlant startup will be documented and dispositioned on the checklists included in the procedures covering the activity under review. Each discrepancy will have a unique identification number and all doci.iments dealing with evaluation and disposition of the discrepancy will reference the identifi-cation number. Resolution of discrepancies will be handled in accordance with controlling procedures. One or more corrective action documents will be issued to report all discrepancies resolved prior to startup.
B. Long-term: Corrective action documents will be written to encompass all corrective actions required for a checklist or procedure and the normal corrective action procedures will apply.
VII. Annrovals
- . ,/ /) ... ** /
Prepared by: -*--~u~-t~~..<: (u ~-<14??5-.
Task Force Coordinator ------
~
Approved by: "
Task Force Manager Approved by:
Director of Quality Assurance -
Nuclear Operations
PALISADES MANAGEMENT REVIEW TASK FORCE Task Force Manager RBDeWitt Task Force Coordinator FWBuckman Review Team Action Team Screening Team NRC Response Team Support Team JPFl nn JGLewis KWBerr DPHoffman RBCherba
APPENDIX B TEAM RESPONSIBILITIES Note that this is a non-sequential compilation of responsibilities. Additional items may be assigned by the Task Force Coordinator as the need may arise.
Review Team
- 1. Assemble safety-related equipment checklists.
- 2. Compare P&ID to checklists.
- 3. Verify Correctness of P&ID (vis-a-vis checklists) - may include mark-up of drawings.
- 4. Review procedures identified by Screening Team
- 5. Identify problems w/ checklists or procedures.
Action Team
- 1. Process checklist/procedure revisions to correct problems identified by Review Team.
- 2. Process corrections to P&ID's from Review Team.
- 3. Implement new su!"reillance procedures identified by Screening Team.
Screening Team
- 1. Sort procedures that have* an effect on plant safety systems. Provide results to Review Team.
- 2. Review Technical. Specification Section 3 for LCO's that involve accessible safety systems equipment.
- 3. List existing surveillance procedures for item 2, or identify needed new procedures.
- 4. Compare identified safety systems from item 2 with prior existing lists.
- 5. Write procedure.
NRC Response Team
- 1. Develop draft response per NRC.letter. Receive inputs from team leaders and Task Force Coordinator.
- 2. Prepare an oral response per NRC letter.
Sunnort Team
- 1. Complete Technical Specification Test Audit. Provide results to Screening Team.
- 2. Develop Equipment/LCD matrix.
- 3. Provide for audits of all actiYities.
APPENDIX C TE.Al.VI PROCEDURES
- l. The following team procedures are required.
Checklist Review - Review Team Procedure Review - Review' Team Safety Realted Boundaries - Review Team Checklist/Procedure Revision - Action Team P&ID Corrections - Action Team Sorting Review - Screening Team Surveillance/Tech Spec Review - Screening Team Matrix Development for LCO's Support Team
- 2. The procedures should identify: actions; persons responsible; acceptance criteria; documentation requirements; needed reviews of documents; distribution of documents/results to other teams; ultimate disposition of records.
- 3. Team procedures are reviewed by the Task Force Coordinator. Changes may be made by Team Leaders, with notification of change t*o Task Force Coordinator (no review prior to change).
- 4. Procedures will be controlled by assigned number and revision status. A single master list identifying approved revisions is maintained by the Task Force Coordinator ..
APPENDIXD - 1 VICE PRESIDENT FOR NUCLEAR OPERATIONS (R B DEWITT)
Education Bachelor of Science in Mechanical Engineering, Tri State University, Angola, Indiana University of Michigan, Ann Arbor, Michigan (Post Graduate Work)
Western Michigan University, Kalamazoo, Michigan Exoerience 1949-50: Junior Engineer, B C Cobb Steam-Electric Generating Plant, Consumers Power Company (510 MWe) 1950-52: Engineering Assistant, B C Cobb Plant, Consumers Power Company 1953: General Engineer, Consumers Power Company, General Office 1953-60: Plant Results Supervisor, B E Morrow Steam-Elect1*ic Generating Plant, Consumers Power Company (186 MWe) 1960: Senior General Engineer assigned to Enrico Fenni Nuclear Power Plant, Detroit Edison Company 1960-66: Assistant Plant _Superintendent, Big Rock Point Nuclear Plant, Consumers Power Company 1966-68: Plant Superintendent, Big Rock Point Nuclear Plant, Consumers Power Company 1968-73: Superintendent of Midland Nuclear Power Plant, Consumers Power Company 1973-75: Superintendent of Palisades Nuclear Plant, Consumers Power Company 1975: Nuclear Production Administrator-Acting, Consumers Power Company 1975-79: Manager, Production-Nuclear, Consumers Power Company 1979 - Vice President for Nuclear Operations~ Consumers Power Company present
APPENDIX D - 2
- DIRECTOR - NUCLEAR ACTIVITIES (F W BUCKMAN)
Education
. 1962 - 1966: Bachelor of Science, University of Michigan
. 1966 - 1970: Doctorate (PhD) *in Nuclear Engineering, Massachusetts Institute of Technology Exoerience 1970 - *1972: Reactor Engineer, Consumers Power Company, Genera.l 0 ffi ce 1972: Senior Reactor Engineer, Consumers Power Campany, General Office 1972 - 1974: Temporarily assigne*d to Project Management Corporation working on Liquid Metal-Cooled Fast Breeder Reactor (LMFBR) research
. 1974 - 1977: Nuclear Fuels A<lministrator, Consumers Power Company, Operating Ser'Vices Department, General Office 1977 -
Present Director of Nuclear Activities, Consumers Power Company, General Office Responsible for all nuclear acti'Vities required to support operation of Consumers Power's nuclear plants, including licensing, reactor physics, safety analysis, fuel specifi-
.cations and fuel performance, and health physics.
APPENDIX D - 3 OPERATIONS SUPERINTENDENT (J P FLYNN)
Education 1964: US Navy Nuclear Power Training Program, Bainbridge, Maryland and S3G Prototype, West Milton, New York 1972: Bachelor of Science in Electrical Engineering, Purdue University, West Lafayette, Indiana 1972: Heart-Lung Resusitation J..975: 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> QA Program Indoctrination, Quality Assurance Program-Nuclear 1976: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Transient Analysis - Supervisors 1977: 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Managerial Economics; 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> Monetary Control/Budget; 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Fire Training 1978: B&W NPP Op for Management; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Multi-Media First-Aid Training 1979: B&W NSSS * ( 7 weeks) ; Mechanical Systems Training ( 11 weeks)
Exnerience 1964-68: US Navy - Electrician's Mate aboard USS John Adams SSBN 620. Qualified Shutdown Watch, Electric Plant Control Panel, Steam Plant Control Panel, Upper Level fu."ffi #2, Auxiliary Electrician. Made eight FBM submarine patrols (PWR) 1972-74: Associate Engineer, Palisades Nuclear Plant. Assigned plant modifications and engineering projects. Shift test engineer during power escalation to 100% power. (PWR - CE) 1974-75: General Engineer, Palisades Nuclear Plant. Assigned plant modifications.
and engineering projects.
1975-76: Senior Engineer, Palisades Nuclear Plant. Assigned as project leader for a group of engineers performing plant modifications and engineering projects.
1976-77: Maintenance Superintendent, Big Rock Point Nuclear Plant (BWR - GE) 1977-78: Operations Superintendent, Big Rock Point Nuclear Plant (BWR - GE) 1978 - Operations Superintendent, Midland Nuclear Plant (BWR - PWR) present Associated Exoerience Senior Reactor Operator License No SOP-2497 - Palisades Plant (PWR - CE)
APPENDIX D - 4 GENERAL MA.NAGER PALI SADES (J G
- LEWIS)
Education 1953 - 1957:
- Bachelor of' Science in Electrical Engineering, Michigan Technica1 University 1961: Computer Graduate Courses, University of Florida 1963: Nuclear Engineering Short Course, University of' Michigan Various other short courses during nuclear plant training period *
. Experience 1957 - 1962: Experimental Test Engineer, Pratt Whitney Aircraft R&:D Section 1963 - 1966: Computer Engineer, Big Rock Point Plant, Consumers Power* Company 1967 - 1968: I&:C Engineer, Big Rock Point Plant, Consumers Power Company 1969 - 1974: Technical Engineer, Palisades Plant, Consumers Power Company*
1974 - 1975: Operations Superintendent, Palisades Plant, Consumers Power Company 1975 - 1979: Plant Superintendent, Palisades Plant, Consumers Power *Company 1965: SRO License ( NRC) , Boiling Water Reactor, Big Rock. Point Plant 1970:* SRO. License (NRC), Pressurized Water Reactor, Palisades Plant
APPENDIX D - 5 SENIOR STAFF ENGINEER ( K W BERRY)
Education 1961 - 1965: *Bachelor of Science in Electrical Engineering, Ohio State University 1968: - Graduate Courses in Nuclear Engineering, Ohio State University 1966 - 1967: Graduate Courses* in Mathematics, Ohio State University 1974: - Nuclear Power Preparatory Training, Palisades Plant, Consumers Power Company Excerience Three Part time employee at Ohio Valley Electrical Corporation summers Headquarters - Assistant to microwave telemetering equipment maintenance 1963 1969: Goodyear Atomic Corporation Gaseous Diffusion Plant Mass Spectrometer Laboratory - development and unusual maintenance
- 1969 - 1970:
- Associate Engineer, Palisades Plant, Consumers Power Company -
assisted I&C Engineer in initial plant checkout of plant instruments
- 1970 * - 1971: General Engineer, Palisades Plant, Consumers Po~er Company -
Test Engineer during initial criticality 1971 - 1975: _.I&C Engin~er; Palisades .Plant, Consumers Power Company -
Plant -
1975 - 1979: Technical Superintendent, Palisades Plant, Consumers Power Company l_
APPENDIX - 6 .
NUCLEAR LICENSING ADMINISTRATOR (D P HOFFMAN)
Education 1962 - 1968: Bachelor of Science in Mechanical Engineering, University of Michigan 1968 - 1970: Master of Science in Mechanical Engineering, University of*
Michigan Enerience 1965 - 1967: Plant Engineer, Dow Chemical Company 1967 - 1970: Senior Reactor Operator, University of Michigan 1970 - 1975: Senior Engineer, Detroit Edison Company .
1975 - 1977: Senior Engineer, Consumers Power Company, Operating Services Department , General 0 :ffi ce 1977 - 1979: Assistant Nuclear Licensing Administrator, Nuclear Activities Department, .Consumers Power Company, General Office
APPENDIX - 7 DIRECTOR OF QUALITY ASSURANCE (R B CHERBA)
Education 1959: Bachelor of Science in Electrical Engineering, University of Michigan Exoerience 1963-66: Plant Engineer, Karn-Weadock Plants, Consumers Power Company 1966-68: Plant Engineer, Big Rock Point Nuclear Plant, Consumers Power Company 1968-70: Start-Up Engineer, Palisades Nuclear Plant, Consumers Power Company 1970-71: Test Coordinator/Plant Engineer, Palisades Nuclear Plant, Consumers Power Company 1971-75: Region Area Superintendent, Traverse City, Consumers Power Company 1975-76: Nuclear Operations Supervisor, General Office, Consumers Power Company 1976-79: General Superintendent, Production-Nuclear, General Office, Consumers Power Company 1979 - Director of Quality Assurance-Nuclear Operations, General Office, present Consumers Power Company
l APPENDIX - 8 MFR ASSOCIATES, INC Three engineers, Willard Grant, Gordon Anderson and Philip Hildebrandt, are doing an independent check of the Palisades Nuclear Plant mechanical penetra-tions and isolation valves.
MFR Associates, Inc provides engineering services to industry and government with particular emphasis on energy and power production. MFR has extensive background in power plants and other fields requiring high technical. standards.
FC - 1 Response to NRC INPUTS Team Leaders Task Force Coordinator
'I!, ~.-
Develop Written Response Develop Oral Response to NRC Letter Outline NRC Resnonse Team NRC Res-ponse Team "i, ,,
Approve Response Present Oral Response Transmit to NRC to NRC Task Force Manager T.ask Force Manager I_
l FC - 2 Checklist & Procedure Review Assemble Safety- Sort Procedures Related Equipment . Screenin~ Tea.ni Checklists Review Team
'I!,
Verify P&ID Correct P&ID Mark-up """ Action Team
~
Rev:Lew Team I
~
,. I I
I
~ ,.
Review Procedures Compare P&ID to Checklists ~- - - - - - - - - - _I _ _;__ - - - -
- Review Team Review Team ..
"l ,
Identify Problems
'I Identif°'J Problems Review Team Review Team Process CL/Proc
..... Revisions to Solve tr Problems ,
,d Action Team
FC - 3 Surveillance Procedures Review TS 3.xx for Accessible Systems Screening Team
~
Compare to Prior Lists Screening Team
~ 'f List Existing TS Test System Procedures/ Audit
~
. Identify New Recommendations Needs Screening Team
" Support Team Develop New h... Procedures/
'fl' Schedules Screening Team
FC - 4 Eq_ui-:::ment/LCO Matrix Develop
.Matrix Smrnort Team