ML20206B915
| ML20206B915 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/12/1988 |
| From: | Keeler G, Jerry Spangler SPANGLER ENVIRONMENTAL CONSULTANTS, INC. |
| To: | |
| Shared Package | |
| ML20206B722 | List: |
| References | |
| FOIA-88-198 NUDOCS 8811160050 | |
| Download: ML20206B915 (191) | |
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4 Attachment #2 i FINAL. l'ItOJ ECT ltH1'OltT : i l Funibl!!ty of Exposure Assessment For The Pilgrim Nuclen:> 1'ower I'lant i t
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Frepared fer t ne .!nsachuse. ts Copartment of M11c Health r r 1 hy I j ! l- 6 Dr. J.D. Spengler and Dr. C.J. Keeler y i t spangler Envirenzantal Consultants Inc, thy 12. 1988 j i t L
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' !.E'iXIP.!A IN y!W MA33AC.fJ5E775 C0A37A!. TOWS Abstract for American Epidentelegic $:ciety ,
tiarca 18. 1987 Stoney Cobb, Richard V. $1 app, C. '. Chaa & latius V61ker Jr. with the assistsace of J. f., Parkias
" Q astal distributica of leukemia adjacent to nuclear installattees has tees observed La tagland, in scatland and La the state of Maine. It seemed possible that a similar sit'uation sight exist sear de Pilgrim ! auclear plant sa Essaachusetts 3ay. The hypede sis was that, as is $4184, the of f tct would be la de towns dowaviad, i.e., aern of the plaat and would begis, sere. five years after acnivation of* the plaat. This plaat went en lias December 1H1.
Cancer registry data, available only for the years 1982a1984, stov SI3L's win 33 percent csafidcaca intervals for tAs five towns north of the plant as followet hema:3peetic and reticulsendothelist cancer 154 (128,204), leukemia 139 (113,224) and eyelogesons laukasta 191 (120,304). Ne sue.h excese occurs island and south along the coast. Mortality data, is five year groupings, show $10l's nat )egna ta be excessive about 1979. Analysis by census tract revents esenstally all the excess incidence in the coastal tracts, deflatsg the affected area as less than five sites vide and abcut 20 sites lous. Occuper.iensi data reveal ne clus t e r'.s g . Vater and silk supplies are maar and de ant fit stis narrow coastal patters. Reported airborne releases fres tae plant are tee esal'. to produce this effect, unless the effluent was held to a coastal distribution by sese seteorslogte pattera. Such a pattern is well ksess ta seteorologtsts. If tais excess leuksuis was caused by radioactive estartal released free tae plant. the releases stsht have been foll;wed proeptly by sese adverse reproductive outesses. The .a rge s t reported releases fres the plant were between 10/74 and 9f 73. In tse peeted 1973 1974 tse inf ant sortality rates
t s t a 's t t mo ri r tou e third, ei a brosse end stcJtont unnus wculo aevect In aedittcit. tito sta unwuad ch.'.:ulation ucule emisstens ever populated are.is
*! sit intaos pwtiwLtation to a 6vv att.a.
C..un. t i ne, stie n.i aMe t".it t own a re the followin,t (tets, Tltat. the se.a treets citrulation is :tg a clossd loop in which e:etsstens sould be trapped and recirtutated. $atend, the ditaction of a sea breete is not constant but ratates in a clockwise direction during the day. The vincs start of f normal ta the shore end eventually bleve parallel to the shore. However, this might preferencial*.y espose populations to the vest and nort.i. Thus a sodt!!ad 'Cobb hypothesis" is probable. 3 Recornmendations
- 1. Installation of continuous recording seteorelegical instruments at additional inland sites in the Piraeuth area should be considered, the parameters sensured should include wind speed and direction. temperature dew point, and solar insolation. The Plymouth airport would be a good candidate
. site for this purpose. Inland sites would help e.haractertze the esa breeze incensity as well as provide ?.mproved netverk for dispersion modeling.
- 2. Exposurs isttorna for emissions from the Ptigria ! Fever Plant can be deterstnad us8kg a !Lrst order approach. A probabilistic modet could incorporate the properties of both a plume dispersion model and available wind frequencies. Area averaged exposures vould be calculated on a relative easts for 4t!!erent distances and sectors around the Pilgria Plant. Senettivity analysis should be performed to determine how exposure scaling La influenced by assumptions about input condtstens. The critical parasecars to be tested are emissions, dispersion coefficients, and sesoscale circulation patterns.
Exposure patterns are Itk+1y to be influenced by the height of the release Jacation (stack vs. butiding vents) sad assuspeters about the averagtng time over which the releases occurred. fased on sensitivity analysts the requirement to reconstruct release data by locatten of release and time of day (hourly average) weu14 he considered. 3.1 Consnients on a Retrospective Study A rettespective study would be listred by:
- 1. ?tse resolution of the esteston data fres Ptigria;
- 2. Inland meteorological observations:
- 1. Anticipated sprcas in concentratter.: may not pesvide sufficient spacial resolution.
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vo em,. m w Qy J Dr. Ce5crah Prothrow 5 tith
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y t Coseta:1ener Commonwealth of Massachusetts Desartment of Pubits Nealth IMI fremont Street loston, MA 02111 Ret Respones to CPH Ntad Theory Analytte ,
Dear Dr. Prothrow 5 tith:
The pAltetty surrounding the release yesterday of the tatsst study in a series dating back two years is ence again drawing unwarranted Itnks between radicattive releases fres Pilgr:e Station and scee Clusters of leukasia tacidence la five towns north of .M1gris Station. Environmental radiation senttoring em,qucted by loston Edisca concany and confirmed by both the Nuclear Regulator i Massachusetts has consistently shown no,v Cownissten and the Commonwealtn ofincre! beyond the beundary of loston Idtson preparty at 711gris.
/,ccording to your departsent, background radiatica levels in the area are helev levels in other parts of the state.
Osatrary to press retorts we believe the latest MOPW wind pattern analysis is j notatallinconsistentwithourcwnanalysts,whitadisputestheprincipa) elements of the Cobb theory. It is 1stortant to note that Dr. Cota P.as stated that unless his wind tracting thtcry is true. ' reported atractne relenses frcs the plant are teo small to presuce thl effect.' ('ncreassa leutetta
- incicenje). I l The Stens & Hobster analysis, ceantastened by lost
- n (discn, never concluded that the wind did not blev ti an everland direction. Cvr analysts aid .
- conclude that there was no tants for the theory that ollutants were tra:ced, rectreulated, or confined to a narrev $6ctrashical ar;ea alcng the northern coast. We belteve tnat the results cf Cr. Spangler's recent report agree ca this taportant issue. ,
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N1y 1.1988 Page two Dr. Spanq1er states on page 2 of his report (attached) that 'the sea breeze circulat'on is n i a closed Icon in which estsitons would be trapped and 4 rectreulated.' (eNnasts in the original) We certainly agree with the study's conclusten that any concentrations of radicactive raterial would be greater within five attes than at greater distancel; but, as noted above, releases from Pilgria have not been suffletent to cause significant radittien levels even at distances of such less than five alles. As a result of these and other factore, including the extensive studies of lov level radiattan by troops such as the Fational Arndemy of Sciences, the it!R Comittee, the NCAP and the ICAP and many other 6ainently qualifted groups of scientists, we must conclude that any 11Ak between reported increases in lautosta and P11gris statica releases is not credible. However we support further studies by CPM to determine the cause of increased etacar incidence, in part because of the hundreds of Boston Idison emelayees and faallies who I!ve en the South Shore. At the s&se time, we hope CPN wt11 esercise caution to avoid ger. orating further unwarranted pualic concera. Very truly yours, p if' ' LC3/ag Attachments [
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'J ED/ SON Pilgrim Nuclear Power Station w w w w wams .
July 27,1988 88-40 4 TO: All Nuclear Organization Personnel , I covered the attached information during our initial meeting with the NRC Integrated Assessment Team Inspection (IATI' serbers on July 20, 1988. It briefly describes the progress we have made over the last twc years and the basis for our request for the IATI. The IATI is scheduled to begin August 8. 1988. I hope you will shaie this information with fastly and friends; they will no doubt have questions for you as we approach restart. R. G. Bird i I : 1 ! Attach =ent l w- s -, _ w - . m - ___ _ __ se- - mm
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. 1 R. C. BIRD - IATI PRttrMTATION ON JULY 20. 1988 i . Good morning.
l I will brief1.v sueu rize the steps we have taken since ' April 12,1986 which resu13ed in our readuess for the IATI to begin, ; and I will discuss our current status. '
- Ne are convinced that there are three keys to success in managing any large, compler organizat?on;
- First high standctds that are undetstood throughout the organizatio0;
- Second realistic plass for achieving t%se standards; and -
- Ihlid a system of controls for mer,uring performance against the stancaid: 1.id plans.
I Ne believe that Boston Edison's Nuclear Organization now meets thosa criteria. ) When I arrived at Boston Edison, my ismediate task was to assess 1 the strengths of the organization and determine the tress that needed i reinforcement. The next step was to assign priorities and direct our I attention and resources accordingly. I Me have continually reassessed our situation, adjusting resources as needet;, and refining the process which resulted in the ft ing of our i Self-Assessment of the Readiness for Restart Report 13 May 1988. Along the way:
- Ne evaluated management practices at Pil;rla and presented our conclusions to the NRC at a September 2f,1987 public meeting.
- Ne determined plans and actions necessary for restart and issued our July 20, 1987 Restart Plan.
- Me condutted in-depth assessments of natntenance and adiological controls and implemented improvement action plans covering both restart-related and long-tern actions.
- Ne conducted investigations and critiques of specific events at PNPS and identified actions to prevent recurrence.
- __ __ . ~ . , m . , . _ , , . t Ne are effectively resolving the restining issues which were identified in our restart readiness self-assessment. Ne have laplemented j and evaluated the improved work control process. The overall results are satisfactory, and a few additional leprovements are being made. He intend to continue the self-assessment process at Pilgris Station.
The long-tern management organization has been defined and almost I all key positions have been filled. All iey managers, section head and I above, ,1 Boston Ediscs employees. l Ne have maintained continuity of work force and u nagement through ( the retention of many talented long-tern Boston Edison employees. : We strengthened management by adding p le who are among the very best in their fleid. There are new annagers Emergency Preparedness, " Security Radiological Protection. Operations Plant Support, Special Projects. Fire Protection, Natntenance. Training, and Quality Assurance. The senior management team includes about a dozen new people who brought with thee over 250 man-years of successful nuclear power ! experience, and some outstanding Pilgria veterans. They are all strong l individuals who have high standards. They work well together and are an , effective team. He have also upgraded the Nuclear Safety Review and Audit Committee f and brought in additional outside members who are widely-recognf zed esperts in their fields. , I The condition of the plant has improved dramatically since the ! I' beginning of the outage in 1986, and the rate of improvement has ' accelerated through 1987 and into 1948. ! ! We have dedicated significant resources to the Satety Enhancement ! Program, which exceeds current NRC requirements and therefore is not a : prerequisite for restart. Our program, which emphasizes nrevention of l core damagg, was a Boston Edison initiative in response to the draf t l "Severe Accident Containment Policy for Boiling Water Reactors ' which i the NRC staff presented to the industry in June 1986. We proceeded to implement new Emergency Operating Procedures based ( upon Revision 4 BMR guidelines because they are technically superior to l the earlier reylstons. This major initiative has been a well coordinated
- ! effort by our Nuclear Engineering. Operations, and Training Departments !
i who used the new plant simulator extensively in their work. l We are very proud of our accomplishments in this program because we l J have significantly improved our capability to effectively respond to i off-normal events in a safe and reliable manner. l i ! We have focused attention on aggressively upgrading those areas that had been rated Category 3 in the early 1987 Systematic Assessment of l Licensee Performance - Security. Fire Protection, Radiological, ! I Surveillances, and Assurance of Quality. We don't believe that any of i these areas should continue to be rated Category 3. l l t 1 \ l
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- No are meeting our goals te coglete work japrove housekeeping and l
,. preservation, reduce contractors increase Roston Edison staffing, and do i high qua11ty work. l Ne are generally meeting our schedule and visitors have commented ! ! very favorably on plant condition, worker attitudes, and our sense of i
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' t 1 Although our work planning capability is not yet where we want it, ane this is still restricting productivity somewhat, we are nonetheless a seeing taproving quality in many of the indicators we use. J As japortant as any other factor, the Operations Department is : 4 ready to support a safe and reliable restart and continued operation. l
' Since last summer, two successive classes of Reactor Operators and !
t Senior Reactor Operators have taken their RAC esans with a 100 percent pass rate. The new Itcenses are currently lleited, but once we are at i power they will be able to meet those condt'Aons. Then, we will be able ! to staff a sis-shift rotation io permit schadiling for future operator i classes to ensure that there le always enoufA oportters in training to t compensate for attrition. ( During restart, we plan to use a four-shift rotation. This permits i an entra Senior Reactor Operator to be assigned to each shift and allows the most efficient use of esperienced operators. The operators look better - they are nov in unifore, and sound l better. Training in formal communications has been effective and is showing clearly beneficial results in improved control and a higher level of nrofessionalism. All four crews have completed training on the revised Emergency [ Operating Procedures. Our operators have been observed as part of our I self-assessment, by INP0 and by the NRC as part of the t0P inspection. Every assessing team has concluded that they are well trained and I prepared to operate the plant safely and reliably. Additional simulator training for normal operating conditions is ongoing. To sum up - we have toes a long way: { Based open our completed self-assessment of iendiness for restart. ( which includes an independent review by INP0 we have concluded that, j upon completion of the actions identified in the Self-Assessment Report i and the Restart Plan. Pilgria Nuclear power $tation will be ready for l safe and reliable restart and continued operation. l l Our conclusions include the following:
- 1. The self-assessment confirmed the validity of the Restart Plan, j
- 2. We identifled some limited areas which show signift: ant l improvement, but which require completion of specific, i well-defined actions for restart.
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- 3. There is leproved performance in all areas rated as Category 3 in the early 1961 SALP. ,
! 4. He have an effective management team with talent and espertence that can match any in the industry. i ,'
- 5. We have done a thorough review and identified a few things left to do this summer.
The responsible managers will now provide the status of , self-assessment actions and of sequenced work and testing to restart. - I
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JUL 29 '88 11:30 PILGRIM HRC RESIDENT P02 ! i,,7-26-if i 12:14 i aancolios.s , PSP 5- 617 747 3473:s 1 ! p.s I
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- ee 39:19 BOSTCN G! SON 94. V.8 MlLEM
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l hlyte.1Hs I For More Information (scs)tt4-4003 (24 Hours) - Llnine Robiness MnFidler l David Tarrantine ; LATilf SALP REPORT C0hf!AMS PROGRES$ AT P! LOR!N i ~ The Nuclear Regulatory Cosmission's latest revlew of Besten (dison I l
' Company's perforstace at Pilgria Station 'rscognises the sucellent progress'l we've made at the plant in the last li months." laid (dison Senior Vice President Ralph G. Sted.
l Sted, a retired rear austral who served under Admiral Nyman C. Rickover. l took over management of Pilstka Station in Plymouth at the beginning of thI 1 NRC review period in Fotevary 1967. He said he was outremely steased at both the taproved ratings ud over ; tone of the SALP (Systematic Assessment of Licensee Performance) i An ffJ l NRC covered the period of Febevery 1,1987 through May 15. IM8. > inspection of cerrent perforumate is scheduled to begin August 8.
'It is clear that the actions taken in the 11 catettrice rated by the NAC l staff are achieving success,' lied said.
Since taking ever at Pilgria, lird has made major management changes, f bringing in a cadre of esperienced nuctoar Navy and nuclear power ! I work with existing toston Edison employees. He said, '!'s proud of the accomplishments of the entire Idtson staff at Pilgrim.' Sted also noted that the compuy hos made physical improvements. a
*!t's out goal f which onceed Federal standards, to enhsato safety perfruance.
xe Piieri. u ines.a it. der and ,e re min, in tne etght dir.ction. l to l both with our safety anhancement program and ranageeent improvem ! 1 kM
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' d 29 '88 11:30 PILGRIM NRC RESIDENT P03 (J. 29 '99 29128 BCSTCN DISCN SR. V.P. N.C.E#t P.2 In a letter to lird eccompanying the report, NRC rettenal administrator j
; W1111t's T. Russell wrote: 'No recognise the progress demonstrtted to date as a ?
result of your entensive effortt however, i continued vittlance on your part is , necessary to achieve ud sustain overall results." Bird said he tgreed on the need for "continued vigiluce." *!t is vital to odr long ters success that we donetetrate for the MAC ud the public that these improvosess will he continued and sustained for the long-ters.' ; the M4C rated Pilgria in 11 catsgeries. Edison showed taprovements in sir ;
- of the the areas with five remaining unchuged at category "I' or category '2".
In the latest report, the NRC did not rate the company in cae area, eutage l maaageunt, an area in which the tespany received the highest category rating *- ) in its 1941 report, i l One category, radiological, was again rated a category 3. but the NRC said i it was "taprovine" ud therefore "indicative of a Itkely change in the l l performance category in the near future." 1 ) No areas declined. ; j- The other areas rated ud the ratings (froa ' to 3 with I being the i j hignost) are: Plant Operations - ti Maintenute ud Modifications - ti l l survemate - :1 tre protection . :: entriency preparednein us j !sproving; security ud Safetuards - 21 tagineering and Technical lysport - 1; i j t.icenstag Activities - 2; Training and @tlification Effectiveness - ti i,
- Assuruce of Quality - 1. '
NOTE: The .;over letter from tW pc and the susmary of the assessment are ' attached. 1 The full test of the 1 ALP Rewrt is available from the Nuclear i Information Office, i
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s . CTTICE MEMORANDUM Boston Edison Company R"G Control Nu:ber To: D)stributton Tro-: ). . A . A r.d s r s e r. _ Date: $/1/88 Dept. Doc. 5038-449 Record Type A4.08 Non-$atety Related
Subject:
Systes Suasary Status Report Updates 01ctr1)utlon: J. A. Seery J. T. A'.exander Systers Clerk A. I;. Swanset. V. $. Clanry R. I. Sherry 7. Gra:10 Attach ent: 1) 1;;end. x ;;. "5yst u Se:ary st atus Report"
Reference:
*) P11 grit ::u ' e ar 7:s ir 5:lt;ca F e st ar t *1an Attached for your review and use are the *atest . a; dates to it.e Syste- Su::ary Status Reports which were ort;1nally sn 1 :,4 as A;;endix 10 to the M:75 ).-
start Plan. The reports reflect she *ost current status of outstanding work ite:s as tra:ked by the Systee speelalls s for telt assigned systeis. As 'he Statien continues to proceed toward restart the report will be u; dated to c.sy current with the status of work pre;tess. Any feedback on the reports is encontaged. Shoutc you have any questler.: re;ardir.; the ir.formatica contained it. : .e reperts, feel tree to cor. tart V. 5. Clane). Systets Engineering Divu len ?.anager, or the assigned Syste-Specialist. JE/t; Wi
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] RFO-7 SYSTKM STATUS SUKKARY R2 PORT System: ; Main Ste . Data Date: 7/28/88 Gi. i u 5 eam Isolation Valves and Upstream Piping) i System Eng Dicroce, V. J. -
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Prepared By: dIdk$$ ' Peviewed By: Approved By: bdhs d4P9_,
- Major Systen Production Vork Completed: f 1
, o Inspect / Overhaul of Safety Relie! Ives (SRV) at Vyle Lab e Design change to Main Steam Isolattsn Valves (MSIV) pilot poppet completed M e Replaced Y.afn Steam supports / snubbers e Rebuild of Main Steam Isolation Valves (MSIV) solenoids complete Significant Systen Issues Addressed:
', e Analog "rip System (ATS) Modification e TP 86-167 Test of MSIV closure accumulators complete w SAV tasting ot Pilot Poppet Material Modliicatlin to prevent pilot poppet sticking Outstanding Systes Post 09tage Work Items:
> e fio outstanding post outa?o work , Significant Systen testing Status: , i e LLE
- of illVs comp'.eted & satisfactory e Cliss 1 Hydro complete & satisfactory a Surveillance 8.5.6.2 Automa:1c Depressuri:ation System (ADS) valves (alt method) is scheduled during Power Ascention
- e 8.M.1-24 MSlV Logic Test (>6004) required after Startup
- e SRV flanges require leak check and visual inspection at pressure e 8.7.4.4 MSIV Trip (at reduced power) required once on line
-e 8.7.4.5 MSIV exercising required once on lina
.- e 8.M.1-14 & 15 MSIV closure (and calibration) required once on line
-- e TP 87-219 MSIV opening test to be performed during Startup to verify proper operation of modified MSIV pilot poppet assemblies O
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A System 1 (V. Df.Croce l continued: Outstanding Comments / Problems:
- - - e Four'SRVs and one SV being removed and sedt to Vyle ' sabs, f or lif t check.
Work Statts e 1 Outstanding Restart MR Is 'Jorking N 14 Outstanding P.sstart MRs Are In Test /Closecut (1; require steam for post work test, 3 in closesout) F I' e' O 4
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FO-7 SYSTEM STATUS
SUMMARY
REPORT Data Date: 7/25/48 System: Il Main Stea: (Downstrea: of Main Steaz Isolation Valves) r System Eng: P. Trepanier j
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Approved By: eW/ f i
" t Major Systen Production Work Completed: t e The (4) moisture separators were inspectef. :nlet and outivt welds v e re dye checked. A1; previously yurmanit+d repairs were sade permanent.
The majority of this work was on level instrumentatien on the soisture separator dra n tanks. - Significant Systes Issues Addressed: e Removal of nine hex nuts which were tack velded to ain steas lines B & C (Nuts tre b.tlieved to hav4 beer part of St.* rtup '"ast apparatus) . Outstanding Systen Post Outage Work Items: e NONE Significant Systen Testing Status: e Post Vork Testing of repacked / replaced valves in Meisture Separator area and steam supply to Staam Jet Compressors in off-gas systes, to be performed when sain steam is available. 0 e
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9' c *- Systec #1 (P. Trepanier) con 1 cued: Outstanding Comments / Problems:
- ,e A pipe hanger supporting the Stea: Jet Air Ejector pressure control valve is currently being redesigned by the Nuclear Engineering Depart-
- ent. Hanger replacarent is scheduled prior to Startup.
e Vork Status ' Outstanding P.astart Software : tem e e-4 0 4 0
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SUMMARY
REPORT System: f2 Reci.culation Data Date: 7/26/88 System Eng: steven Bernat
, Prepared By:. M $ M Reviewed By: k ku d fo<thi$
' Approved By:_
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. Major Systen Production Vork Completed:
e Motor Generator (M-G) sets refurbished e Installed Anticipated Transient Without Scram (ATVS) modifications i to drive :otor breaker (reliability izprovement) Alaras for pump motor vibration and bearing oil level separated e ' e Pucp A oil cooler changed out e condensation problem above panel 2225B eliminated Significant Systes Issues Addressed: e flRC concern over field breaker trip f ailures addressed by adding a trip to :he drive motor breakers and original equipsent manufacturer overhau' of AKT Breakers at their facility
- e systes reliability improved by refurbishing M-G sets Outstanding Systen Post Cutage Work Items
- Leak check va-ious valves at pressure e investigate seal purge flow control valve perforzanJe at pressure Significant Systen Testing Status:
e 3 Surveillance tests need to be completed
*'-e ATVS testing currently in progress
'5 % a Surveillance testing remains to be done on ATVS (4 tests) e other surveillances are up to date e
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.anding Comments /Probless:
Pump flange inspection during reactor heatup after seal welding both pump cov,er flanges. Seal welding preparations are underway. .i
,, Work Status ,
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N8 Outstanding Restart Y.Rs Re:ain To Be Vorked
\ 3 Outstanding Restart MRs are Vorking N
-J, 25 Outstanding Festart MRs Are In Test / Closeout
.' 18 Outstanding Restart Software Itans i
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H ... t RFO-1 SYSTEM STATUS
SUMMARY
REPORT , h , System: #J Control Rod Drive (CRD) Data Date: 7/22/88 System Eng: Jeff Calfa 1 Prepared By: S- '
'? Reviewed By: wha Approved By: /// dh'atZ.
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Major Systen Production Work Completed: e 'B' Control Rod Drive (CRD) Pump and Motor overhauled i e 15 Control Rod Blades replaced (10 with haf nium tipped hybrids)
- e 16 Hydraulic Control Units (HCUs) had 101, 102, 112 isolation ;
valves rebuilt (SIL 419)
- 23 CRDs removed and rebuilt e 96 Seras Valves had diaphrag:s replaced (IEN 86-109),
e 145 HCUs had holdown bolts rep 14eed and torqued (LER 87-006-0) e 145 HCUs had 117 and 119 vent valves inspected Significant Systen Issues Addressed: e HCU Holdown Bolts (LER S7-006-001 e Scram valve :aintenance (IEN 36-199)
~
e HCU Isolation V&lves (SIL 419) e CRD vent valves Failure & Malfun: tion leport l i Outstanding System Port *Jutage Work Itess: e Restoration of stabiligir.g velves to balance system pressure Significant Systen Testing Status: e Leak checked CRDs during Hydro e Scram testing performed after Hydro e All surveillances up to date e Need to restroke all rods to verify movement O 6 9 m
. . . . . . . . . . . < - t.... . . . . . : ..:. . . -. .. . . . ~ : -~-- ----
s System 83 continued: Outstanding Comments / Problems:
% Resolve IEB 38-05 Indeterminate Quality Issue on s'JV Flanges ( tlc R- 8 8 - 59, 88-60) e Work Status: 3 5 Outstanding Restart .MRs Ar.3 In Test / Closeout h6 Outstanding Restart Software Items /
e 4 .M 6
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4' n .# RFO-7 SYSTEM STATUS SUKKARY REPORT V- System: 44 Sa=pling Data Date: 7/25/88 System Eag: D. Terraro Prepared By 1- co i > Reviewed By: b# ~ %L3N (NS Approved by: II - l Major Systen Production Work Completed:
$ e Installation of two new State-of-the-Art saeple racks and chiller units
- Reactor Vater Cleanup (RVCU) Sampling and Analysis Rack 01 (C-121). a'.sd the condensate and Feedwater Sampling and Analysis Rack
#2 (C-122)
A e Fost Accident Sceple System (PASS) flow seter 8661 installed Significant System Issues Addressed: i e TASS pip:ng heat trace and cateria*. inspection outstanding Systes Post Outage Work Items: e Grab sa:ple espability: Changed the installation of the RHR sample sinks from a temporary to a permanan'. condition. Significant System Testing Status a TP 87-131: Post modification testing of samp'.e sink C-122 completed , e TP 37-177: Post modification testing of sar.ple sink C 121 eSapleted l Outstanding Comments /Probless: e lived saeple sinks placed in automatic service e Vork Status .
. _ t "' $ Outstanding Restart MRs Remain To Be Worked i
'3 2 Outstanding Restart MRs Are Votking
$ Outstanding Restart MR$ Are In Test /Closecut .
1 ~ outstanding Restart Software Items j s O ( r
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s t RFO-7 SYSTEM STATUS
SUMMARY
REPORT 1 System: 65 Station Ltg Data Date: 7/26/88 System Eng: Richard Cahill , Reviewed By dr a Approved By:_ -
!Mm Major Sys a Production Work Completed: ,
10CFR50 App e Power Pack Ltg ,
.0D for remot shutdown
' Significant System Issues Addressed:
e Addition of energency lightings (PDC 86-45) s Outstahding Systen Post Outage Work Itent: j ',
- NONE ;
l [, Si'nificant g Syste1 Testing Status: ) e NONE 4 C Ontstanding Consent,g/f toblens: : 1 .1 Outstanding Restart MRs Remain To Be Vorked l [, 2 l 3 Outstanding Restart MRs Are In Test /Closcout i j
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9 s RTO-7 SYSTEM STATUS
SUMMARY
REPORT System: 86 Teedwater Data Date: 7/25/88 , Systea Eng: Karl Axelson Prepared.By: . 82O% , i Reviewed By: . I 13 Er' Approved By: _ Idd// #>>'f'
,. Major Systen Production Vork Completed:
a Refurbished Teedwater (TV) pump notors e Refurbished TV pusps (including new zechanical seals)
- e Inspected and modified TV pump discharge check valves e Replaced soft seats os main TV envek valves with new material
; e Made permanent repairs to various Tursanited leaks '.' e Performed extensive Ultrasonic Testing (UT) on TV piping e Refurbished 'A' TV Regulating va'va .
Significant Systen Issues Addressed: e High Energy Piping Erosion /0errosiot. (:EN 86-100, SOIR 87-03) _ e Check valve problems (IEN 36-01, 50ER $6-03) e Leakage through main TV chve'r valves . Outstanding Systen Post Outage Vork Itens: ' e NONE - Significant S/ sten Testing Status: l e TP $7-215 TV pump trip - working l e Procedure 2.2.119 TV syste Flush - after TV system repairs ; i Outstanding Comments /Probleas: : l e Vork Status ; 4 Outstanding Restart MRs Remain To Bv Vorked i 1 Outstanding Restart MR Is Vorking 7 Outstanding Restart MRs Are In Test / Closeout .' i
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SUMMARY
REPORT
.. Systes:t 7 Turbin6 Bypass Data Date: 7/25/88
- #15 Gland Seal 45' Turbine Generator & Aux' Syste: Eng:C. Jungelas "see also System n'! Prepared By: h57b DDFu%r] L4 '
? C ,.~
R+viewedBy:gi. i Approved By: h s Major Syster Production Work Completed: e High (* ssure (HP) turbine: complete disassembly, steam path parts
; sandblasted and non-destruct 1sely tested, diaphrages repaired, shell in-spneted, and rotor inspected r 'A' Low Pressure (LP) turbine: complete disassesbly, steam path parts sandb11sted and non-destructively tested, diaphrages. repaired, inner caking hori: ental joint steam cuts repstred, 24 last stage pins re.laco4 geontinued on next sheet)
Significant Systes Issues Addressed: e '.? Tichine shaf t axial keyways ultrasonic test performed o L? Turbine last stage buckets inspected and 2A pins replseed e Generatot hydrogen seuls repaired e Reduction of set point centrolling the bypass of th6 saras signals on Turbine Control Valee Tast Closure & Turbine St p Valve Closure as recommended by GE SIL 423 s { Outstanding Systes Post Outage Work Items: I e Turbine Control Adjustments per System id3J Significant Systes Testing Status: 1 e Generator Air Test complete 1 e Generator core nonitor test to be complete during Startup j e Turbine trip testing - in progress Outstanding Comments /Probless: o Confirm acceptability of HP diaphras repair e T. valuate Turbine Generator Torsional Testing per GE TIL 1002 .. e G e
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, Systen 47, 15, 51 (C. Jungelas) continued:
7 e Work Status 6 Outstanding Restart MRs Remain To Be Worked ?
. C Outstanding Restart MRs Are Working j 2 Outstanding Restart MRs Are In Test / Closeout'
- . 1 Ot.tstanding Restart Software Ite galor System Production Voy,k Completed f) e "A" L? Turbine (continued) 4
$ Inspected inner casing and otter hood, inspected LP rotor and buckets, ,. torqued bolts, replaced all diaphram packing and packing springs, in-
;. spectid atmospheric relief diaphrams, replaced exhaust hood spray
' !.. nor:les and inspected extraction line expansion join:s. e Gener ator - perf ormed High Potential Testing on Stator, rep *. acid ! hydrogen svals and insulated holt sleeves and washers, cleaned and in-spected collector rings and brush rigging, instsl3ed n.v shaft grounding ( straps, repaired ain lead box manways (hydrogen leaksi, replaced gas-l kett. on all oil pi-ing, cleaned 2 hydrogen coolers. 1 i l- e Altacrex - replaced shims under Alterrex, cleaned < eccler heat ex-changer, greased and torqued bus bars, inctalled so'td p*1els under str.cor base to correct airflow paths, repairec air coo 14r vent "alve io le ak, replaced ti!BCO valves in rectifier banks.
- e Bearings - bearings inspected, T-9 hearing ring repaired, various ther-
, ec<ouples replaced, thrust bearits checked for wear and shaft grou.14 ng. i e Cauplings - replaced Alterrex coupling, shizaed to t1rrect alignrent at j A&B coupling. e *urning Gear - inspected, clearances and alignment checked. 4 i e Lift pumps - replaced 5 pumps, calibrited pressura switches, replaced inlet check valves adjacent to bearings, changed filters, drilled air vent holes on suction side pump elbows. e Stator Cooling System - inspected 'A' & 'B' pumps, replaced bearings, seals, bushings, guides and mechanical seals, replaced both pump motors, ,. replaced filters, replaced rectifier bank shut off valves, calibrated gauges and flowneter.
]
System f7, 15, 51 (C. Jungelas) continued:
' e control valves - all 4 valves overhauled.
e Main stop valves - #1 and #2 ;nspected and tested. e Combined Intercept Valves - #2 and #4 inspected and tested. s e Seal 011 System - Inspected Xain' Seal 011 Pu:p (XSOP) Recirculating Seal
, 011 Pump (RS6P) and Etergency' Seal Oil Pump (ESOP), replaced rotating parts, inspected MSOP and RSOP motors, replaced motor nearings, replaevd Seal Oil Vacuu: Pu=p (SOVP), rebuilt level control valve, rebuilt pres-sure governor and cleaned vacuu: tank.
e Tront Standard - Replaced Mechanica*. Pressure Regulator (P.PR) bean
, valve.
9 i P O e
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T t* RFO-7 SYSTEM STATUS
SUMMARY
REPORT Syster: 85 Augmented Offgas (A00) Data Date: 7/25/88 Systes Eng: F. H. Young A ,/, j
. Prepared By: W/ M m4*e%
kh# Reviewed By: Iti.M;LC ar' 1* !
.. Approved Sy: Ikd# d #dh4F
, Major Systen Production Vork Completed; ,f db ;
e Augnented Offgas (A?G) Refurbtshmant I:4chanical conplett, I electrical, and Instrumentation in progress) ; e "A" reco binir, preheater, and condensar vessel
, Non Destructive Examination (NDE) I e Reco:biner vessel sup; ort replac+zint e Small bore pipe replacement Significant System Issues Addressed: ,
, I e Hydrogen Pecombiner Area Equipment Cor.d;tior. ,
e A0G H analy:vr operation , e off;as condenser level. control outstanding Systen Post Outage Work Items: a Complete refurbishment of 'A' reco:biner train ; k Significant Systes Testing Status
- t be Post work testing of repaired equ;prent for MR closeout pending
- i. e Systes pressure test to PVT leak repairs t
! a offgas Flow Calibration 8.E.8 after MRs work li I Outstanding Consents /Probless ; e?* Cycle 8 operation will be with refurbished single train (limited ! J redundancy) ! e Vork Status ( i 2 Outstanding Restart MRs Are Vorking i 1 f j 3 Outstanding Restart MRs Are In Test /Closecut [ 'd
.1 1 Outstanding Restart Software Ites .
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h RFO-7 SYSTEM STATUS
SUMMARY
REPORT Syst e::: 89 Contain:nent Atmospheric Control Data Oate: 7/25/88 System Eng: D. Terraro Prepared By: m D[ OF Reviewed By: //d2h7, I I Approved By: 8/ /--- a , - . . Major Systen Production Work Completed: e Backup 111trogen Syste:: installed and tested i
- 1 Significant System Issues Addressed:
i l e ~nstalled Backup Na supply to increase Na purg+ capacity on sit +.
- Cotstanding Systen Post Outage Work Iteas:
j e t:0 t Significt.nt Systen Testing Status: i- [ Perfor: equiprent checkout / lineup sf Liquid :lttrogen I e l' l Vaportzer TrcJer L Outsti.nditag Comu nts/Probless: 1 I . e Work Status
; Outstanding Restart MR Is Vorking l j 3 Outstanding Restart MRs Are In Test / Closeout ;
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I RTO-7 SYSTEM STATUS SU10(ARY REPORT i Systes: #10 Residual Heat Removal (RHR) Data Date: 7/01/38 i System Eng: Steven Bernat
' Prepared By: Mw%M '
Reviewed Sy! //th j, Approved Sy: . i Major System Production Work Completed: i i e Containment spray hesdwr no::1+ and drains redesigned
. e Pumps rebuilt c e Valves 235 and 36A/B replaced e Valves 68B and 28A & B repaired e Nu:erous relays replaced -
e B heat exchanger flance fursanited e B heat exchanger bottot. head drain cut and capped e Provided calibrated leak off capability for low pressure piping e Corrected 10CTR21 single failure concern for mini:u.. f'.ow valves e New disks installed in 33 A/B valves f e Rework minimum flow cht.ck valvss to prevent suction piping : pressurization while in shutdown cooling Significant Systes Issues AddreJsed: e Small bare piping vibratien addressed
- e Root cause and corrective action of cracked welds and loose bolts in low pressure ICCS ,
o confirmatory Action Letter (CAL) 86-10 issues a Hydrodynamically tested inboard check valves (64A/B), one refurbished, both left with : era leakage e Pump impeller wear ring and motor surge ring braeXet erleking a:dr(ssed ; outstanding Systen Post outage Work Itees: I o RTO-8 Add position indication to check valver, 1001-68A and B ! RTO-8 Add small bore pipe supports to certain lines in the drywell. N e ; t Significant Systen Testing Status *
*% e urveillance test eed to be completed e M 1 other survei a are up to date i > r i
' ~
. . :.... .r: ... 1-..- '
1 p . - , 1 Syste- 410 (S. Bernati continued: Outstandicg Consents / Problems:
,,, e Investigate failure and cracking of XO-100'-2SA & B valve yokes and backseats (NCR-88-31/401 .
'*s e Address :Inimum flow issues per IE3-38-04 e Vork Status Oitt standing Restart XRs Ress.. To 3e 'Jorkid
~
'-- 14
- 13 Out st anding Rest art .5Rs Are '.'or.<.n; 30 Outstanding Restar: "Ps Art :n Test /C.os. oat . .
33 Outstanding Restar- Software ::=..s
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RTO-7 SYSTEM STATUS StnotARY REPORT System: 411 Stand By :. quid Control (SBLC) Data Date: 7/02/38 ] System Eng: J. Calfa Prepared By: M.e AM4Jrs-
) Reviewed Sy: .d#/M .a Approved Sy:
, Major Systen Production Vork Completed:
ge Replacet:ent of $3LC solution (higher isotopic) to meet requitecents of 10CTR50.60. e Installed T'.ovmeter in return to storage tank line.
- e Rebuilt PSV 1105A/B discharge relief valves par 3.M.4-80 o Corrected 1101-1 indication proble
Significant System Issues Addressed: ) { e Resolm discharge erzlief valve failures I !, Outstanding System Post Outage Work Items: 1 e NOUE Significant System Testing Status: I e All Tech Spee Surveillances up to date Outstanding Comaeftts/ Problems:
'e Repair to "3 accumulator restrains operability and surveillance testing e Vork Status 1 Outstand 12y 70 start MR Is Working 3 Outstanding Restart MRs Are In Test / Closeout 3 Outstanding Restart Software Items e
0 e e
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SUMMARY
REPORT Syste : 812 Reactor Vater Clean Up (RVCU) Data Date: 7/28/SS , Systee Eng: J. Purkis Prepared By: .kt-
~
t ? Reviewed By:A- WA JF Approved By: g Major Systen Production Work Completed:
}- e P:!s perf orced on: MO-1201-5. .*0-1201-2. 10-1201-50, MO-1201-35 1 s F.any system manual valves reworked j ., e ilew RVCU holding pump installed e DP:S 1243, 1244 calibrated & lines flushed e Systet tiv .ns for Hydrogen Vater Che:istry completed ;
i . ! Significant System Issues Addressed: )
- i. e Tiushing of lines to DPIS 1243, 1244 to zinimi:e potential for spurlo2s
. ?C*3 actua:lon of RVCU (Hydraulic Snubber Issue) [ ; Outstanding Systes Post Outage Work Items: [
]; i e Special Test of CV1239 to be performed during power ascension l r Significant Systen Testing Status: o Co:pleted satisfactory LLRT (on all syste valves) 4 e Co:;1sted Hydro ' )s. e All Technical Specification (TS) Surveillances up to date Outstanding consents /Probleris: j l a
\e Resolution of DPIS bydraulic snubber settings e Work Status 1 Outstnading Restart MR Remains to Be Worked ,
4 f 2 Outstanding Restart MRs are Working h I l 1 Outstanding Restart MRs Are In Test / Closeout ,i l
+ Outstanding Restart Software Items . } l.
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f e i . L #' . . , i a RFO-7 SYSTEM STATUS SUKRARY REPORT System: #13 Reactor Core Isolation Cooling (RCIC~> Data Date: 7/22/88 ' System Eng: R. Mattos Prepared By: b4/ l [ Reviewed By:,
> L*TTaab5 Aope - .c By:
Major Systen Production Vork Coopleted:
, e Turbine 5 year Preventive Maintenance (PH)/crerhaul i e Motor Operated Valve (MOV) overhaul /Movats testing e Gland seal leak-off system restored e Turbir.e insulated wich Asbestos f ree -aterit!
Significant system Issues Addressed: , t e Increased Turbine Exhaust Set Point e UNR 86-06 residual flow issue roo: cause identified e RC 86-21 Logie Systee Tunct:en:1 Tests ; i e UNR 86-21 simulated automatic actuation test ' e I.E.B. 85-03 M0V (Limitorque) switch setting t e I.E.B. 88 minimum flow issue ' Outstanding Syste. Post Outage Work Items: e Operability Testing as noted below e RCIC turbine "cold quick" start EC G7-51-02 (procedure 3.5.5.1) Significant Systen Testing Status: e Completed: TP 47-198 RCIC Testing using aux, steam satisfied: 4.5.5.3 (full flow at 150 psi) 8.5.5.6 (A.S.P. operability of pu.; and valves) 2.2.22 (overspeed trip test) e Normal surveillances due prior to startup as per MSTP e Q 85-03 Q 7esting at pressure to be schedu14d O
. .- ..'.,_,. ..c . - - --- - - - -- - ' -- - - - -
O p .. System 13 continued: Outstanding Comments /Problens: e Vork. Status 5 Outstanding Restart P.Rs Re.tain To Be Worked 21 Outstanding Restart ARs Are In Test /Closecut O e
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I 1 l RTO-7 SYSTEM STATUS
SUMMARY
REPORT System: 814 Core Spray Data Date: 7/25/38 l i Syste: Eng: J. Gaedtke/D. Rosinsk: Frepared By:
,pf -
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-^
Reviewed Dy: 4 N.M Approved By: ' sk//- l Major Systen Production Vork Completed: '~ [ j e Test return check valves 1400-3$/2*4 . dises replaced '! e HTA Relay replacements e MOV 1400-4A and 4B yoke bonnet replacements l , Significant Systen Irsues Addressed: i 4 e Core spray test return check valve conce::ns l e MOV 1400-4A and 49 yokv f311ure root cause concerns i e Procedure / drawing discrepane:es l e Hanger and support inspecticas l e Pump Impeller wear rings inspceted and replaced to sddress *GCCC concerns j
- e Surge ring brackets on one motor Stator inspected and no crachng found ,
i l Outstanding Systen Post Outage Vork Items: i i i e RTO-8, Correct vertical orientation of Core Spray Cheek Valves 1400-)$ i and 1400-214 s RTO-8, Address Core Spray 1400-3A anc 98 position ind:encion i Stulficant Systen Testing Status: e 8.5.1.3 failed due to M0-1400-25B handswitch ta:,1ure tMR 88-14-22 i scheduled this week) 4 Outstanding Comments /Probless: e Address minimum flow issues per IEB-8)SA i i L I' . . e Work Status t l I
. 4 Outstanding Restart MRs Remain To Be Vorked l l
Outstanding Restart MRs Are Vorking i 3 Outstanding Restart MRs Are In Test / Closeout .. i j 1, outstanding Restart Software Ites - l i i I I i l [ l l 2 j I t
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SUMMARY
REPORT Systes: 416 Ixtraction Staar Data Date: 7/25/88 l 517 Teedvater Heater Vents & Drains Syste: Eng: P. Trepanier , Prepared'By: M r obsw Reviewed By: I kl Approved By: s ,o Major Systen Production Work Completed: f e Perfor: sed maintanance on extraction steam bleeder trip f valve cotor operators i e Re; aired dump sparger for feedvater heater E-105A e Completed additional non destructive examination to confirm no erosion ISignifictnt Operating Experience Report (SOER) - 37-03: High energy pipe inspections;. ! l Significant Systen Issues Addressed: [ e 'Aotor operator =aintenance [ e Pipe vrosion inspections co: plated satisf actorily (50ER-87-03) t [ Outstanding Systes Post Outage Work Itens: j e lJo outstanding sys.te post outa7e work f L Significaut Systes Testing htatus: : o None outstanding Outstanding Comments / Problems: ; e Vork Status j i 1 Outstanding Restart MR !s In Test / Closeout I f I
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;8 RFO-7 SYSTEM STATUS
SUMMARY
REPORT j System: 813 Condensate Da a Date: 7/25/88 Systes Eng: Karl Axvison 3
.i
- Reviewed By: 1 M .
Approved By: !// Major Syste's Production Work Completed: 7 l e Extensive UT of condensate system piping .
' e Replacement of cond tivity elements and recorders l
; e inspected condensate sump discharge cheek valves ,
e Refursished 2 of 3 condensate pump motors L
, e :nspected & refurbished internals on 4 of 7 condensa e de:inerali:ers (Conde:in) (other 3 are scheduled)
- Significant Systes Issues Addressed:
e Erosion / Corrosion addressed (IEN 86-106 SOER 67-03) ' [ e Conductivity neasurement equipment upgraded
, e Potential check valve degradation addressed by zultiple :
i
- ssts/ inspections (SOER 86-03)
Outstanding Systen Post Outage Work Items: i , , e NONE i Significant Sfstem Test ag Status; j e TP 37-271 Condensate deminerali:er conduettvit) aler.ents - working s T? 37-203 Pre-op cf condensate desineralitwe ver ~ valves - work.ng ! j e Procedure 2.J.119 TV systes Flush - after scheduled repairs l l Outstanding consents /Probless , o Couplete condensate deminerali:er refurbishment i e Work Status .I l 4 Outstanding Restart MRs Are In Test /Closecut ; 1 1
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- RFO-7 SYSTEM STATUS
SUMMARY
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System: 119 Tuel Pool Cooling Data Date: 7/25/88 ; i System Eng: J.Gaedtke/D. Rosinshi
. - PreparedBy:h.--
_- -) f. Reviewed By: kft3J1k6 : Approved By: . . . J Major Systen Production Work Completed: f t,,
-e New spent fuel racks installed - increased capacity ;
- ., e TP cooling backflush f:,1ter placed in service i i i l Significant Systen Issues Addressed: l e Reviewed adequacy of brace on fus*. pool heat exenanger ,
e Disassembled fuel pool cooling pu p B to correct vibration -
- Tuel pool liter - precipitate buildup at drain l l Outstanding Systen Post Outage Work Items:
e Inspect neutron absorbing material in futi racks . (IEN 37~43) ; 1 r f Sigaificant Systen Testing Status: i f e NONE 1 i Outstanding Comments /Probless: t l i 2' ,
- e Work Ststus (
t
- \
No outstanding Restart Vork Remaining ; l 1 s. 1: t 4
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n ( . i l RFO-7 SYSTEM STATUS
SUMMARY
REPORT j Syste:: #21 Desinerali:ed Vater Data Date: 7/25/88 : ( l System Eng: K. Axelson
- f I Prepared By: b2 8[h -
Reviewed By:_ . f . Approved By:_ / - . . m .] . Najor Systen Production Work Completed: . I
- e ::or4E j;
i , Significant Systes Isstes Addressed: [ i . 1,02 ! e
- [
l ' l i Cittstanding Systen Post Cutage bork Items: Y I e Co.:plete analysis of catetaining portable trailer vs. repairing or ! replacing Makeup De:ineralt: r Syste: f i ! Significant Systee. Testing Status: {
- t
.I e :10:1E l Outstanding Consents /Probless: [ l ! i e e Work Status j No outstanding Restart Vork h i ) . l t .- j i l . . i l f 1 l, , i 1 1
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RFO-7 SYSTEM STATUS
SUMMARY
REPORT ! Syste-: 80: Main Generator Hydrogen Data Date: 7/;5/88 1 i Syster Eng: C. Jungelas ; Prepared By:- i dC -
~
Reviewed By: ._ Approved Sy: ,f Major Systen Production Work Completed: f
), o Hydrogan Vater Cher. stry tie-in complete
! e Hydrogen flow totalizer installed e Hydrogen seals on main generator reworkad/ repaired Sigaificant Systes Issues Addressed:
, o Myriregen leakage - Main Generator i i
', Outstanding Syste.m Post Outage Work Items: [
t
, e IMne idaatitied !
4 Significant Systes Testing Status: e Wydrogen Vater Chemistry tie-19 post work testing - in progress i e Mun ;enerator air in-leakage test - c.mpleted satsstsetorily ! t outstattir.g Comments /Probless: ! i a Work Status 6
, 1 Outstanding Restart MR Is In Test / Closeout ;
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?
RFO-7 SYSTEM STATUS
SUMMARY
REPORT ; System:023 High Pressure Coolant Injection (HPCI) Data Date: 7/22/88 Systes Eng: ?.. Mattos - Prepared By: /DMA ' Reviewed By: k 746 Approved By: _ hb/ / is'-r - l
,, Major Systen Production work Completed: ;
o Instal *ed exhaust line vacuum breakers (PDC 85-59) f o e Turbine 5 year P.M./ overhaul ;
. e MOV overhaul /X0 VATS testing .
e Re-work check valves 2301-45 and 2301-74 ; 4 e Turbine / piping insulated with as?<stos free sateria' ' 3 Steam inlet piping align =ent and turbine radowling I
, e HPCI Room and Susp Room decontaminated and painted e Installed Torus level /te:p. indication at Alternate Shutdown Panel (ASP) l Significant Systen Issues Addressed: ;
t
. e IFI 85-18 Vater hammer issue addressed e RC 86-21 logic sytten functional tests [
e 'JNR 86-21 Simulated autonatic actuation test
. e I.E.B. 85-03 MOV (Limitorque) switch settings t o I.E.B. 88 minimus flow issue !
Outstanding Systen Post outage work Items: I e 0perability Testing as noted below
; --e NPCI Turbine "cold quick start" C $7-51-0. (Procedurt 8.5.4.1) e S*op valve balance chamber adj at tw00y 1 3.M.4-81) :
r L Significant Systen Testing Status: l e Completed: Temporary Procedure f81-199 HPCI testing using ! aux steam satisfied: ! 8.5.4.3 (full flow at 150 psi) r
, 8.5.4.6 (Alternate Shutdown Panel operability of pump 6.. valves) !
2.2.21 (overspeed trip test) l e Normal Surveillances due prior to Startup IEB-85-03 MOV Testing at pressura to be scheduled e
.f e itB 88 Test of AUX Boiler tie-in flange (PDC 87 TP 88-39) [
4 e f i ! i 7
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Syster 23 HPCI continued: Outstanding Comments / Problems: e Resolve _Indetere.inate Qual;lty of Flange per I!B-83-05 e 'Jork Status , 9 ) Outstanding Restart ::Rs Re:atn To Be Worked 1 Outstanding Restart MR Is Vorking 44 Outstanding .\astart T.Fs Are :n Test /Closecut D O e
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l RFO-7 SYSTEM STATUS
SUMMARY
REPORT Systen: 804 Heating Ventilating & Data Date: 7/25/88 ' Air Conditioning (HVAC) Systa: In;: ;*. Perite r O' '
. f q j - ,.
Prepared By:- kblAN/VI Reviewed By: -db6!<AL^e -
,pr-
, Approved By: T l Major Systen Production Vork Completed: # t e Secondary Oontainment Dampers upgraded 0 e Preliminary Air Balance - Turbine Building (Bldgl MVAC system i Significant Systen Issues Addressed: . s Control Rooz e:ergency ventilation single 'ailure and operability e Loss of Control Room HVAC (Procedure 2.4.149) ! e Control Room texperatures I e Turbine Bld; HVAC balance i
. e Inhanced second*.'y containment integrity l Outstanding Systen Post Outage Work Items:
o Cosprehensive .VAC air balance including Control Roo: and I:ergency Diese Genera . v. m.ves , L 5 Significant Systen Testing Status: l r e Control Root ventilation TS Operability / surveillance current [ to date [ e Secondary Containment leak rato - complate [ e Prasary Containment temperature monitoring - at attrtup l I l I L h e
, .. , : . , . . . . . ... .. , ..- . .. ... ... . - - .. . . . . . . . .w
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. Systes 824 (M. Perito) continued:
Outstanding Comments / Problems: e Work Status 14 Outstanding Restart MRs Are :n Test /Clasicut 5
- outstanding Restart Software :ttes 9
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4 . 0 RFO-7 SYSTEM STATUS
SUMMARY
REPORT System:025, Condenser Vent & Drains Data Date: 7/25/88 150, Main Condenser Syste: Eng: P. Trepanier Prepared By: dm4 ti : -
) Reviewed By:. J .
- l '[ 7""
Approved By: s Major Systen Production Vork Ccapleted: [ e Rew orked Condenser Tube Sheets including co:plete removal of deteriorated tubssheet coating from all (4) condenser tubesheets and i - the application of a thicker, stronger coating, both 6" downtube and on tha tubesheet surfaces. The waterbox sacrificial anodes were also I replaced. Icontinued ) 'j Significant Systes Issues Addressed: o Condenser Better: ant Prograt Outstanding Systen Post Outage Work Itees:
, e NONE Significant Systen Testing Status; e Helius Leak Test of Main Condenser (during Power Ascension Program) , e Steas Jet Air E;eetor 9erfor:ance Test (during Power Ascension Program) e A*1 surveillances are complete to date Outstanding Comments /Probless: ,
e TP 88-24. Hydrostatic Testing of the Main Condenser Steam Side, was performed on 5/11/88 to determine the source of chloride in the hotwell. Pour tubes were identified as leaking during this test, and several extraction line dump / drain valves were identified as having packing leaks. Repair work is ongoing. e The circulating water pipe expansion joint on the 1-1 waterbox outlet side was oeserved to be leaking during preparation for the Main Con-denser Hydro. Replacement of this expansion joint as well as inspec-tions of the remaining expansion joints is currently is progress. , e 9 4
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Systea 805 & 52 (P. Trepanieri continued: e Vork Status
. Outstanding Restart F.R R : sins To St Verked
, 6 Outstanding Restart :tRs Are *r. Test /Closecut
?
.lalor, 51siv:n Produet ton Ec,ry Corpleted jcontinued):
. The main condenser stea: jet air ejectors were overhauled e Broken reach rod indicators were repstred, flange surfa:es were
, . elesned and valve gaskets were replaced. (4) primary and (2) secondary vapor valves were removed and inspected. Pri ary stea:
admission valves were replaced.
- Twenty hotwell conductivity elements and their associated recorders dere upgraded e A main condenser interna'. inspection was performed and several da.ta;.d hotwell spargers were repaired .
O e' O
i i i RFO-7 SYSTEM STATUS
SUMMARY
REPORT Systva:s26 Condensate Transfer Data Date: 7/25/88 ! i I Systo 4 J: K. Axelson [
~
Prepared By: !/fI[Aw Reviewed By: _ Approved By: '"? Major Syt # 'n' .h s 4 )>rk Completed: ! e ll0NE , Significant Systes Issues Addressed: l a NONE t Outstanding Systen Post Outage Work Items: i e NONE l r Significant Systes Testing Status: [ t
, o Not.*I t t
f Outstanding Comments /Probless: t r e Vork Status I I No Outstanding Restart work ( t 4 O l t I l
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RTO-7 SYSTT.M ST!.TUS
SUMMARY
REPORT Systes:f 7 Circulating Vater (CV) Data Date: 7/25/88 System Eng: K. Axelson , Prepared By: a k828e ! 8teviewed By: . Approved By: , Major Systen Production Vork Completed: , e Returhished CV Pu:p . Motors o Replaced shroud on A CV Purp [ , e Replaced Seavenging Syste:,pipin e overhauled Vaterbox Inlet, Outlet, and Crosstie valves e Replae4'd waterbox inlet and outlet tv.pura'ure elements , e Recoated condenser tubesheets , Significant Systes Issues iddressed: e Degradation of Scavenging syste:
- e Sea water inicskage to condenser l e Eroston/ corrosion of CV pu:p shroud '
i Outstanding Systen Post Outage Work Items-I e B CV pump shroud upgrade during Refueling Outage-8 1 4 l Significant Systes Testing Status: j e TP 87-19) Seavenging Pu=p Perfornance'fest pendtag ( t ! Outstanding Coements/ Problems: f e Work Status l 3 outstanding Restart .MRs Renain To Be Worked ; 3 Outstanding Restart w.Rs Are In Test /Closecut l Y 4 1
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II' , +. # ..., l i L RTO-7 SYSTEM STATUS
SUMMARY
REPORT System:l:4 Screenwash Data Date: 7/22/88 System Eng: K. G. Lane - f Prepared By: [ Reviewed by: n . 'A] L
^
Approved By: _ ~f Major Systen Production Vork Completed: $ e Changed pump svals from racking to mechanical seals
. e Refurbisaid t:avel:ng screens Significant System Issues Addressed: .
e Dar.a;4 to . tors from high motsture/ salt environment Outstanding Systen Post Outage Work Items: o Replace ent of screenwash pump actors with heated :otors e Refurbish:ent of chlorination / dechlorination system o Evaluate check valve performance history Significant Systes Testing Status: o Syste= testing is up to date as of 7/22/88
. e Test spool piece is installed in 'n' strainer inlet itne for continuing evaluation of improved piping matertal Outstanding Comments /Probless:
e Vork Status tio outstanding Restart Work 9 e
' s- . . . . . . . , . ..,t_.. t.'., a . . ,. . .. ... . . ~ . . . , . . . . . , . . . . . . _ . . .. . _ _ .?. 2 -
o 8 .. i I RF0-7 SYSTEM STATUS
SUMMARY
REPORT 1 Systes:f29 Salt Service Water ($$V) Data Date: 7/22/81 Systes I.ng: K. G. Lar.e , Prepared By: 1[I '
?
Reviewed By: t. . ; Approved By _ M I7 % Major Systen Production Vork Completed: , i e Inspection, repair and selective replacer.ent of $$V piping (partial interia repairs - above and below grade) e Hydrostatic testing of both loops e UT inspection of accessable piping (100% inspection) e Partial screenhouse restoration i Significant System Issues Addressed: l e SSV piping degradation i e $$V pump vibration e RBCCV/TBCCV Hx tubesheet erosion , Outstanding Systen Post Outage Work Items: o Pump b.seplate renewal e NED design ef f ort to correct pump vi' station in RTO-E i e NED design effort for upgrading $$V piping in RTO-8 ! e Complete Screenhouse restoration post Startup > Significaat Systes Testing Status: i e All surveillances are up to date as of 7/22/88 except TP 47-54 and Pro- l cedure No. 8.5.3.2, Section 6.1 for P208E which is currently under i repair. l P 208A in vibration alert range (MR 88-29-2.
. P 20 E shutof f head degraded s,s.) 2 - repairs in progress (xr. 25) f i
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e e. System 829 continued: Outstanding Comments / Problems: e Need resolution of IEB-i&-05 Indeterminate Quality Flange issue (NCR-88-46)
- Vork Statts
([ ) Outstanding Restart ,tRs Ra:41n to Be Verked Outstanding Restart .9Rs Are In Test /Closecut
)
2 Outstanding Restart Softwar+ Items d 0 O e
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9 RFO-7 SYSTEM STATUS
SUMMARY
REPORT l Systez:430 closed Cooling Water (CCV) Data Date: 7/22/88 Syster. Eng: X. G. Lane Prepared By: k .h . 4 ' -
?
Reviewe,d By: A%, -- ,b i bhI~ ; r Approved By: M % [ ,
' Major Systen Production Work Completed: ;
" e Retubed 'A' Turbine Building Closed Cooling Vater (TBCCh) Heat Exchanger (HK) <
- Plugged tube leaks in 'B' TBCCV Rx and 'B' Reactor Building Closed Cooling Vater (RBCCV) Ex e TBCCV pump seals changed fre packing to mechanical seals e Major areaker calibration, overhaul and trip adjustment :
e "B" RBCCV Hx tubesheet to divider plate refurbishment l e Overhauled 'A' & 'C' RBCCV purps a Significant Systen Issues Addressed: , e Hanger and breaker lug discrepancies .
- e Syste leakage from TBCCV corrected !
e Ta11ure of auto start HTA relay in RBCCV due to wiring discrepancy ] e RBCCV pump /=otor coupling failure ! a- ' Outstanding Systes Post Outage Work Items: l e TBCCV side stream filter replacement / upgrade j I j e 11eed proof run of new procedure - RBCCV Ex thermal performance conitoring (3:PG-1054) ! f Significant Systes Testing Status: ; Systes tests up to date as of 1/22/88 e j l ! l 1 I I i I
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Syste: 30 continued: Outstanding Comments / Problems: e T&"R lio. 28-160, increasing activity in R$0CV e Vork Status s 1 OutstandingRestartMRhessir.sToBe Verksi 3 Catstanding Rastart .MRs Are In Test /C'oswout 3 Outstanding Restart Software :tems 4 9 e e
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RFO-7 SYSTEM STATUS StnotARY REPORT l Systes:031 Instrument Air (:A) Data Date:7/25/88 l System Eng: R. H. Young : Prepared By: M. - l Reviewed By:_ N . Approvid By: h . /-" Major System Production Vork Completed: ' l l e Replaced compressor K-104A e ovethauled compressor K-1046 i o overhauled cospressor K-111 e Repaired / replaced systen drain traps and Y-strainers t
- e Inspected all air rece. vers !
) e Installed portable air compressor connection (PDC 87-32) I e Replaced int 4ke filters . e Replaced dryer pre / post filters { e Air dryer X-160 overhaulel i e Diesel driven portable ec: pressor staged for use ; Significant Systen Issues Addressed: I l er IEN 87-28, Air Systen Problems at LVRs, issues: i e development of periodie natntenance program (in progress) [ e upgraded temporary air compressor connection - i' e revised Loss of Instrument Att procedure ; e 50ER88-1, Instrum ir System Pailures (prelist, ary review complete,Cactionspendtn-Outstanding Systes Post Outage Work Items: Completed Backup Instrument Air Supply System Tie-in e Overhaul / repair air dryers e Repair leaking isolation valves
%o Address low level internal system contamination j t.
Significaat Systes Testing Status: ', f Post work testing of repaired equipment for MR closeout in progress e Compressor capaetty tests to e completed as MRs closeout I o I e All other testing up to date
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$ys:6e f.4 continued:
Outstanding Comments /Probless: e F*,d NED response for,i.e sys e2)qJality parameters per IEN-&7-28 e kork Status 1
- Outstanding P.stt : . irs Are In Test / Closeout 1 Cutstandin; .Restar: 3citware Ite:
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RFO-7 SYSTEM STATUS $UIOLARY REPORT Systes:f)2 Service Air Data Da*e: 7/25/$8 Systs: Ing: R. H. Young Prepared By: - eu m
> Reviewed By: ,
j Approved By: Mb P.ajor Systen Production Work Coepleted: r ~ e 14 paired blower X-1058 e Repatred blower K-105A significant Systes !ssues Addressed: , e Develop:ent of co:prehensive ?.< progra. (in pre;ress4 Outstanding Systes Post Outage Work Items: e Address low level internal systes conta:1natten Significant Systen Testing Status: e N0!?I Outstanding Consents /Probless: e Vork Status 2 Outstanding Restart MRs Are Working t o 4 ' = - - - _ _ . _ _ . _ _ _ _ . _ _ _ . _ _ _
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4 ... , f RPO-7 SYSTEM STATUS
SUMMARY
REPORT , 1 , Systes:037 Turbine Lube 011 Data Date: 7/25/88 i Syste: Eng: C. Jungelas i 4 Prepared Sy:_bNb%E/dj. . r I Gq - 3 livviewed By: M. MtIE } 1 ppt;ved By: 2 Major Systen Production Work Completed:
- j
, t J e Main 011 tank drained and cleatad !
e Lube oil pumps inspected !
, e Lube oil pump inlet bereens removed i
!, e Lube oil vapor extractor disassembled ar.d inspected i e Luce oil flush completed ! I e Lube oil purifier disasse: bled, cleased, inspseted and. repaired
- l l e Servo enclosure intarnals inspected ;
i i ! Significant Systes Issues Addressed: g t l e Lube till flush completed , Outstanding Systen Post Outage Work Items i i e None identified f ' l 1 Significant Systen Testing Status: { I' s Lube oil testing is done in association with Syster., $1 - Turbine : Generator & Auxiliaries [ r
! Outstanding Coaseats/Probless: ;
i ! e Work Status i i l I 1 5 Outstanding Restart MRs Are Working , 1
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3 .. f RFO-7 SYSTEM STATUS
SUMMARY
REPORT
)
Systests)8 & 61 Diesel Generators & Data Date: 7/25/88 fuel Oil Systen Eng: V. Swan Prepared By: 3rb t
^
n.,1..ed ,y: Ac JrLA Approved By: Major Systen Production Work Completed: e Emergency Diesel Engines rebuilt e Increased fan blade pitch for engsee cooling e Replaced Poly-Chlorinated-81phenyl 011-tilled (PCB) transformers e Installed Blackout Diesel - Significant Systen Issues Addressed: 't l e E'evated engine operating temperature Prelube pump iailures e a Outstanding Systen Post Outage Work Items: l 'N e Provide design revision to allow loaded Surveillance Testing of a Blackout Diesel Generator (DG) i significant Systes T* sting Status: e All daily and monthl), surveillances up to date o Monthly and Quarterly Preventive Maintenance (PP.) up to date
; e Blackout Diesel iceeptance Testing completed outstanding Comments /Probless:
o Vort Status J 3 Outstanding Restart ARs Renaan To le Worked
% 1 3 outstanding Rostart MRs Are Working 14 Outstanding Restart XRs Are In Test / Closeout .-
1* Outstanding Restart Software Items
. . .-..s.- . . . . . . , . .*; .!.-... .- '..-. - . . . .. .- -4 .- - . ,.
4 1 RPO-7 SYSTEM STATUS
SUMMARY
REPORT l System:145A Neutron Monitoring Data Date: 7/25/88 ; Syste: Eng: J. Yingling Reviewed By' Approved By: hW Major Systen Production Vork Completed: ~ s/P ' l
~
! e All eight Inttreediate Range Monitors (IRMs) and ! drytubes replaced e Three Source Range Monitors (SRMs) and drytubes replaced ! e 11 Local Power Range Monitor (LPR.".) strings were replaced ! e Traversing Incore Probe (TIP) tubing reinstalled, pressure tested, J friction tested, drive control units FM'ed, System ran electrically, [ and calibrated y e SRM/IRM drtve mechanisns rebuilt - [ e LPRM Undervessel cables replaced with sineral insulated cable Significant Systes Issues Addressed: [ t i e Top loading vs. bottom loading of SRM/IPMs Outstanding Systen Post Outage Work Itenst j e NONE Significant Systen Testing Status: ( 1 t i
,. o LPRMs and cable - TP 87-55 final tire domain reflectometer testing , and Current Versus Voltage (I-V) curves, during power l
) ascension to complete Post Work Test (PVT) for 20 Priority 1 MRs ; e 3 Rod Block Monitor (RBM) MRs need PVT with mode switch not in shutdown t
- Outstanding Comments / Problems
- e Work Status j t
, 7 Outstanding Restart MRs Remain To le Worked I
1 7 Outstanding Restart MRs Are In Test /Closecut F j 1 outstanAing Restart Software Item .' F j
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,! RFO-7 SYSTEM STATUS
SUMMARY
REPORT System: 8455 Reactor Protection System (RPSI Data Date: 7/25/58 Prtrary containeant Isolation System (PCIS) l Syste Eng: 0. Edsll.auser , [ Prepared By: [ [l[hgh l-Reviewed Sy: FEE"-- A., g ghe, '
, Approved By:. !M / . P.ajor Systen Production Work Completed: f !
e Inst W.ad ATVS ?.edwater Trip ! e Installed Analog Trip Syste: ! e Insts'.'.cd A*VS High ?rassure Trip of Peeire [ e Insts'.'.sd Reference Leg Moditication [ e PC:5 Model CRl:0A Relay Co;l replacen nt - t Significant Systes Issues Addressed: l e PP3/?CIO teproved by rep'.acement of Barton/Yarway '. eve'. trsnstitters ! e llef6:en:a leg flashing reduced by moving ref. leg outside contain ent {' e ATS trans:tttu problems (valving in'.o service following calibration) eliminated with installation of head cht: bars allowing "wet" eali- [ brations , i outstanding Systen Post Outage Work Items: l e NCHE Significant Systes Testia? Status: t i e Surve'.11ance testing is current or scheduled for startup by MSTP i e Neutron Test of new RVL containment penetration to be scheduled i Outstanding Consents /Probless: e Rapid Service Information RSIL 012 (31) and SIL-462 {
- Rose:ont transmitter "ringing" (
e Need to cosplete HTA relay inspection progra: 9 l l r
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o l 4 e. system 45B continued: _ . - . . . - e Newd results tro.. ost Work /$tartup Test Tet Revivd') e Vork Status 13 Outstanding Restart MRs Re: sin To Be Verked 4 Outstanding Restart MRs Ark Vorking J8 Outstanding Restart MRs Are :n Test /c'.oseout i Outstanding Priority A MP. open 6 O O 6
. ..? . . - ...n.... . . . . . . . . . . . . . . . . - . . . ...- .. . .. ......~:.
it o RFO-7 SYSTEN STATUS
SUMMARY
REPORT Systus: 845s* Nuelvar Boiler Instrumentation Data Date: 7/25/88 Systs: Eng: J. Edelhause-Prepared By: ,
.m. 2__,,,__
?
Reviewa(. Sy: 23P~- O EP A e ae . Approved By:_ k >' s Major Systen Production Work Completed: /#
. . Installation of sodification to reference '.e; e Installation of new Control Roon recorders l Significant Systen Issues Addressed:
o Common zero for reactor water level e Referenca legs moved outside of centstn=ent to eltranate flashing outstanding Systen Post outage Work Items: e NONE Significant Systen Testing Status: e L 263-51A & B require PVT .! e Sury,13. lance testing current or schetuled fe.: startup by j Master Surveillance Tracking Progra: (MSTPI 1 outstanding Consents /Probless:
'-e Need resolution of DPIS Hydraulic Snubber Settings e Need resolution of Code Qualifteation for Excess Tiow Check Valves e Work Status 10 Outstanding Rtstart MRs Renata to Be Yorked 1 Outstanding Restart MR Is Working i ) Outstanding Restart MRs Are In Test / Closeout 1
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- RTO-7 SYSTEM STATUS SUNItARY REPORT Systes 045D Reactor Manual Control Data Date: 7/2$/86 f System Eng: E. Almeida !
Frepared By:M.
- _ --
j
' Reviewed By: M _
Approved by: M Najor System Production Work Conoleted: s CRD position indicit.ng probe cables replaced , L i
. t Significant Systes !ssues Addressed: [
t e Upgraded reliabi'.ity of CP; , sition indicating probes f I i outstanding Systes Post outage Work Iteas l e NONE l i b i Significant Systen Testing Status: l e Testing complete to date l i Outstanding Comments /Probless: ! l e Work Status j 1 Outstanding Restart MR !s In Test /Closvout k \ t l \ l l h h t f I i i l .
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0 ... 1 I RFO-7 SYSTEM STATUS
SUMMARY
REPORT [ Syste:: #45E Radiation Konitors Oata Date: 7/05/83 ; l System Eng: J. Yingling ;
- i ,
Prepared By: M% f
'. Reviewed By* - - - Approved By:
Major Systen Production Vork Completed: i
. t e NU iAC Process Radiation Monitors installed l e NUNAC log radiation monitors installed l e Replaced sample pu:ps for Main Stack Vent (MSV) :
e Replaced sample pumps for Reactor Su11 ding Vu t (RSV) ( 4 significant Systen Issues Addressed: - f I e Rest:ed the MSV & RBV pu:ps , < e NUMAC instrumentation replacement upgraded the j
*og
, Padiation Monitors (LRMs) & Proevss Radiation Monitors (P7"si [
[ Outstanding Systes Post Outage Vork Items:
- e NONE i 1 i
! Significant Systen Testing Status:
i e Main Steam PRMs and off Gas PRMs need osce/ cycle calibration with . radiographers source (schedaled) Outstanding Comments /Problets: l
*
- Repeated refuel floor vent monitor spurious downscale/ trips under review. ,
l [ e Vork Status . t I i 1- % 2 Outstanding Restart MRs Remain To le Worked ! . 2 Outstanding Restart MRs Are.In Test / Closeout ' .. l
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'. RFO-7 SYSTEM STATUS SU10LARY REPORT System:f45T Reetreulation Flow Control Data Date: 7/25/88 System Eng: J. Yingling
. Prepared By: A= _. l
?
Reviewed By* #L r-- -
~
Approved By: - l j Major Systen Production Work Completed: [ ' l
,o Rectre M-G Sets completely rebuilt i
Significant System Issues Addressed: i e Revised operations start sequence procedure to prevent incomplete ; sequence trips " [ outstanding Systen Post outage Work Items: ! e NONE f Significant Systen Testing Status: e Up to date f I i Outstanding Comments /Probless: l l e Vork Status i k 1 Outstanding Restart MR Is In Test / Closeout r
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RFO-7 SYSTEM .TATUS
SUMMARY
REPORT ( system: f45I Reactor Vater Level (RVL1 Control Data cate: 7/ 5/88 l l System Eng: J. Yingling [ s 1 . d_ - I Frepared Sy: ri 1 --e (f V > .i ReviewedSy:g(>- .}j ( t
- A; proved by _ _- l Najor Systen Production Work Completed: _ l 1 f
e Analog Trip Systet installed e Water Level negerence legs moved t f i i 3'ignificant Systes Issues Addressed: e Ref erence legs soved outside dryvell to elint. ate flashing j ,. r Outstanding Systen Post Outage Work Items: l i e NCNE } t Significant Systen Testing Status: f l, i e Testing up to date ! e 8.E.6 aust be completed prior to startup , Outstanding Coenents/Probleast [ e Work Status i l No Outstanding Restart Work Remaining l h
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. I RFO 7 SYSTER STATUS
SUMMARY
REPORT l Systes: 846 Electrical Alternating Current (AC) Data Date: 7/25/88 , t System Ing: D. Harris i i w Prepared lyt ._2 7_ ! 8vviewedl[ . V a
/ Approved By: /* % f Major Systes Production Work Completed: f i i
f e Breake6s calibrated ! e Added Mtero Versa trip units to 480 V load center Nodel AK breakers e New coordination data was developed by engineering and implemented for system protection ! e New proceduras were devtloped to- breaker testing , j e A new sequence of ev:nts recorder was install (,4 in the switchyard: j for improved analysts of dirtribution system transients i e Equipment Qualif:, cation valtdowns identified various components ! that require repair / replacement, 3 e Station Black out Diesel installed " e switchyard insulators have been coated with Room Temperature f Vulcani:ing Rubber (RTV) to inhabit flash over ! i Significaat Systen Issues Addressed: I e "atntenance on breakers for switchgear and load centers improved
. f e The addition of a Black out Diesel, switchgear A8, and motor control ;
eenter $40 4 f Outstanding systes Post Outage Work Itens: [ e None f I Significant Systen Testing Status { L e All testing up to date (excepting degraded voltage modification post ! work) l l i
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Systes 46 continued: Outstanding Cossents/Probless: e Silicon 'cron:t bolt steple inspection to 4ddress II:1-58-11 e closecut of re; airs / replacements fro 1 E0 walkdowns e An outstand n; T&MR for the degrad.d voltage relays will require a change in the Technical Specifications and a sodificatten e Vars Status - 78 Outstsnd n; Restart MRs Remain to 5 Vurked 7' Outstnad:n; Restart MPs Are Vorking 5 Outstand:nq 7estart MPs Are In test /Closecut 1 Outstandtn; Restart Software Itet i t l t I 9 l
3
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1 o RTO-7 SYSTEM STATUS
SUMMARY
REPORT
*:846 Station Direct Current (DC) Data Date: 7/25/88 Eng: R. Cahill !
Prepared By: Jkh / Reviewed By: "
. Approved By: '
IAs Major System Production Vork Completed: r#~
; s' Procedure 8.9.8 (Battery Rated Load Discharge Test) 125V "A", 250V ; e Calibration Testing of'10 DC Breakers ! e Procadure 8.Q.4-1 (D,7,D.8,D9 Environmental Test)
Significant Systen Issues Adaressed:
^
e Relay house 125V batteries replaced e Installed fuse & fuse clips on control circuits at alternate shutdown circuits e Silicon bronze bolt sample inspection to address SER-12-88 Outstanding Systen Post Outage Work Items: e Procure Equipment and Perform Battery load profile testing. Significant Systen Testing Status: e Procedure 8.9.8 for 125 V "B" Battery (in progress) e All other testing current or scheduled by MSTP e Determine Scope and complete DC Breaker calibration tcoting (in
. progress) e Need to perform TP to investigate DC Crosstalk (Testing)(Scheduled)
Outstanding Comments / Problems: e Need to per*orn inspections of Terminal Strip Stab Connections (scheduled) e Work Status 5 lutstanding Rastart MRs Remain To.Be Worked 1 Outstanding Restatt MRs Are In Test / Closeout O e e
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. RFO-7 SYSTEM STATUS
SUMMARY
REPORT
.a System:848 Stendby Gas Treatment Data Date: 7/26/88 System (SBGTS)
System Eng: M. Perito- . I Prepared By: kRT' Reviewed By: th d2 Vde Approved By:. J /' Major Systen Production Vork Completed:
$ e Standby Gas Treatment System Modifications ; e teccedary Containment Damper upgrade Significant System Issues Addressed: ,
e S3GTS Single failure criteria e SBGTS Operability e SBGTS Logic system functional testing e SBGTS Simulated automatic actuation e Secondary Containmant integrity e Replaced non Seismically qualiflod HGA r. ays Outstanding System Post Outage Work Items: A e Install vital area (SBGTS Room) access card reader Significant Systen Testing Status: e Tech spec operability /surveillances current to date e TP 87-128 Post Modification acceptance test of SBGTS modifications complete i Outstanding Comment.s/ Problems: e Need to replace obsolete timing relay to establish seismic qualification
, e Work Status l
, 4 Outstanding Restart MRs Remain To Be Worked N , 2 Outstanding Restart MRs Are In Test / Closeout .- T Outstanding Restart Software Items ? - l l l
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t . . J' . - t RFO-7 SYSTEM STATUS
SUMMARY
REPORT Syste.1:#49 Tuel Handling Data Date: 7/24/88 Syste: Eng: P. Mary
?
Prepared By: bdfd $ Reviewed By:M J/* J Approved By: d r ! l'Z$" a r Major Systen Production Work Completed: e Fafurline Bridge ra,alaced with enhanced design e Refueling co:plet4 Significant System Issues Addressed: - e Addressed non-captured items on Bridge outstanding Systes Post Outage Work Items: e No post outage work items Significant Systes Testing Status: e All surveillances current Outstanding Comments /Probless: a e Vork Status No Outstanding Restart Vork 0 e
+
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SUMMARY
REPORT System:#50 Containment Data Date: 7/22/88 System Eng: R. Mattos Prepared By: M
> keviewed'By: D xks Approved By: ) /-+
Major Systen Production Work Completed: ' e Torus vent around SBGT (5025 valve not installed as of 5/6/88) e Penatrations rebuilt (mainsteam lines /feedwater line) e Drywell water level / Torus press indication Secondary Containment Damper Upgrade e Significant System Issues Addressed:
- Drywell liner inspection completed satisfactory e Torus walls (inner) inspection completed satisfactory e Torus walls (outer) inspection completed satisfactory outstanding Systen Post Outage Work Items:
o Completion of direct torus vent modification Significant Systen Testing Status: e Secondary containment verification required (prior to startup) e Successful integrated Leah Rate Test (ILRT) e successful drywell/ torus vacuum breaker test Outstanding Comments /Probless: e Vork Status outstanding Restart MRs Remain To Be Worked 3 Outstanding Restart MRs Are Working t 8 Outstanding Restart MRs Are In Test / Closeout l l 1
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SUMMARY
REPORT I System: 854 Reactor Vessel Data Date: 7/24/88 System Eng: P. Mary Prepared By:-
; } Reviewad By: b -
Approved By: 6d[ #amy Major Systen Production Vork Completed: # e Rerueling complete o Class 1 systen Hydro complete e Hydrogen veter chemistry system installed e Incore probe installed for sampling core water 4 e Reactor vessel water level instrument Modifications complete
, e N-16A nozzle repaired .
e Replaced vessel dry tubes (also replaced IRMs & SRMs) Significant Systes Issues Addressed: e Reactor cyclic Duty Monitoring Program instituted e QC performed extensive In Service Inspection (ISI) of vessel internals. Results satisfactory except for one cap screw weld which was repaired. Outstanding Systen Post Outage Work Items: e No outstanding post outage work remaining Significant Systen Testing Status: e All surveillances current Outstanding Comments /Probless: o Work Status 4 Outstanding Restart MRs Are Vorking 8 Outstanding Restart MRs Are In Test / Closeout (8 steasing retest) 2 Outstanding Restart Sof tware It6ms (field complete) ,. O 4
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SUMMARY
REPORT System: 868, 69, 73, 74 Data Date: 7/25/88 Hydrogen Vater Chemistry (HVC) Crack Arrest Verification (CAV) Extended Test System (ETS) System Eng: K. Hemeon
?
. Prepared By: 2-e . b .m (
- . v Reviewed By: M L C Approved By:
Major Systen Production Vork Completed: e Physical Installation of Systems / Equipment e Hydrogen Storage Tccility system installed e Hydrogen Piping into Turbine Building systes installed e Extended Testing System installed . e Hydrogen Vater Electrolytic System installed e- Hydrogen Vater Electrolytic System installed e M.isc. Piping Modifications Significant Systes Issues Addressed: - e Enhanced sampling equipment for improved Chemistry control e Systems P&ID Vendor Review e HVC Temporary Modification Review /Valkdown outstanding System Post Outage Work Items: e Hydrogen injection system start up e Incore probe monitoring e CAVs/HVC base data generation e New Identified field changes to piping systems e Development of Integrated Test Plan Significant Systen Testing Status: (to be approved, scheduled & performed) e TP 87-132 "ETS Controller Check-out" e TP 87-104 "ETS Calibration of Sys. Inst." e TP 87-145 "ETS Pre-operation Startup" e TP 87-233 "G.E. NUMAC Sys. Controller" e TP 87-236 "Electrolytic Pre-0p/Startup" e TP 87-183 "Instrument Calibration" ,. e TP 88-06 "Temporary Procedure for Purging, Tilling, and. Leak. . Testing the Hydrogen Storage Tacility
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k r . System 68, 69, 73, 74 continued: Outstanding Comments / Problems: e Equipment number designations e Investigation of NUMAC/ hardware & Software Interface problems e Work Status > No outstanding Restart Vork 4 9 e8 e e O e
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Status 8-1-88 1-SYSTEMS OUT OF CODNISSION l
. l
, Sy1 System Descrintion Reason Out of Commission l
, IUL. !
o Relief valves removed for testing 1 Main Steam o MO-220-1 and MO-220-2 drain valves out for limit switches > 2 Recirculation o Drained for pump flange seal welds. o ATHS Testing , 3 Control Rod Drive o Corrective Maintenance of 8 Pump 3 (CRO) ! 6 Feedwater o Repair Reactor Feed Pump (RFP) trip ; K101A relay , o RFP A out of service for corrective maintenance t o RFP C out of service for corrective maintenance 10 Residual Heat Removal o Drained for K)V 28A, 288 maintenance. (RHR) 11 Standby Liquid Control o Isolated for Local Leak Rate Testing (58LC) 13 Reactor Core Isolation Cooling o MOV 48 and 49 out of service for (RCIC) service for breaker testing t .. 14 Core Spray ("B" Train) o 8 Core Spray pump out of service for , A-6 degraded voltage modification. 15 Gland Seal o Exhauster discharge valves out for ( planned maintenance. - j 52 Containment o Torus hatch open I l 19 Fuel Pool Cooling o Out of Service due to RHR system ,
- being drained
- I 23 High Pressure Coolant Injection o 250VOC Battery out of service ;
(HPCI) ! l' 27 Sea Mater o A pump out for water box 1-2, 1-4 tube repair I 28 Screen Wash o 8 pump out of service, for ! corrective maintenance i [ 29 Salt Service Water o 'E'pumpoverhaulinprofress
- l 46 Electric Power o Degraded voltage modifications ,
250 v CC 4ttery A-6 ' 51 Turbine Aux, o Vapor extractor out of service i l l t r
. . .w ..: .......u.. . . : .. .. . . . ~ . .u. . . . .. . a 52 Main Condenser o 1-2,1-4 tater boxes tube plug repair 61 Diesel Generator o 'B' DG out of service for maintenance, o isolation of buss A-6 Note: Reactor Water Clean-Up System inservice for Chemistry Control. One Train of Core Spray System available for coolant injection. Core Spray and reactor water clean-up and let-down to main condenser available for batch feed and let-down cooling and temperature monitoring. One Train of Back-up AC Power (Diesel Generator) available.
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., NRC BULLETIN 88-07: POWER OSCILLATIONS IN BOILING WATER REACTOR i 4 This bulletin requests the following actions be performed.
Within 15 days of the receipt of this bulletin, ensure that all licensed 1. R0s and STAS performing shift duties be thoroughly briefed regarding the uncontrolled power oscillation event at LaSalle 2 on 03/09/88.
- 2. Within 60 days of the receipt of the bulletin, verify the adequacy of procedures and operator training programs to ensure all R0s and STAS are cognizant of a) Plant conditions which may result in uncontrolled power oscillations.
b) Actions which can be taken to avoid those plant conditions. c) How to recognize the onset of uncontrolled power oscillations. b) Actions to be taken in response to uncontrolled power oscillations. In addition, the adequacy of instrumentation relied on by the R0s to recognize the symptoms of the onset of uncontrolled power oscillations must be verified. Within 30 days of the completion of the above actions, a letter shall be 3. sent to the NRC, confirming the completion and implementation of those actions. This letter must be sent under oath and affirmation.
- 4. The evaluation of the adequacy of procedures, training programs, and instrumentation shall be documented and maintained at the plant site for a period of at least 2 years.
Estimated Action Activity Comoletion Status e Train all licensed R0s and STAS 07/21/88 Complete performing shift duties
- Evaluate adequacy of procedures. 08/23/88 training programs and instrument ation
- Submit Final Response to Bulletin 09/23/88 Status Requalification training module 88-0-RQ-09-01-10 "Power Oscillation in BHR's" was prepared and delivered by July 21, 1988 to all licensed operators and STA's currently performing shift duties. This training specifically addressed all objectives to both the 15 day and 60 day training requirements, i
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a NRC BULLETIN 88-08, "THERMAL STRESSES.IN PIPING
!! < CONNECTED TO REACTOR COOLANT SYSTEMS" 3
- 1. Within 60 days of reciept or prior to achieving criticality (whichever is
. later) licensees review unisolable piping connected to reactor coolant ; systems (RCS) and determine if the piping could be subjected to temperature distributions that could result in unacceptable thermal stresses.
- 2. If such piping is identified:
Hithin 90 days of receipt or prior to achieving criticality (whichever is later) examine nondestructively or provide a plan for examination of the c welds, heat-affected zones and high stress locations, including geometric discontinuities, in that piping to provide assurance there are no existing
. flaws.
- Plan and implement a program to ensure that the piping will not suffer fatigue failurt during the remaining life or the plant.
- 3. A report must be submitted to NRC 30 days of completion of item #1 describing tne results of the review and a schedule for completing the item #2 actions.
Action Estimated Plan Activity Comol a tion Status e Review system configuration 8/29/88 Hork1tig and original design analysis documentation to determine if this situation may be present at - Pilgrim e Determine extent of non-destructive examination to be conducted (if any) TBD e Provide response to NRC confirming conpletion of ist action and schedule 9/28/88 for revising actions PHX/amm/2252
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1 e. NRC BULLETIN 88-05 J b Perform a review of the appropriate procurement and material records (CMTR, l HRR, HRIR, P0s, etc.) to identify any potentially non-conforming material. Evaluate any discrepancies and resolve any non-conforming material through analysis, material replacement, or other appropriate action. Estimated Action Activity Comoletion Status Item Reauired for Start-uo e a) Determine applicability of Bulletin 06/20/88 Complete as a restart issue based upon ASHE Code Case
~
- b) Complete review of records. 07/10/88 Working Develop a complete list of "Q" 07/15/88 non-conforming materials.
' c) locate "Q~ non-conforming materials 08/05/88 Horking in plant, warehouses, or elsewhere.
d) Determine suitability of the 08/12/88 materials for their intended service and provide justification for restart and/or continued operation. e) Develop plan and schedule for 08/12/88 or replacement, as n:cessary.
- Final Response to the Bulletin 09/13/88 Status The BECo records to be reviewed have been sorted on a P.O. and receipt inspection document basis for screening and prioritizing.
The NRC has issued Supplement I to Bulletin 88-05, the supplement reported preliminary test results. It limits the scope of the problem to pipe flanges and fittings and alerts the industry to preliminary test results that indicate some tested flanges for or PSI failed to meet the minimum requirements for ASHE code certification. The supplement also defines reporting requirements for utilities. NEO has formed a team of technical, licensing, and quality assurance personnel to locate, sample, test, analyze and repair material from the suspect manufacturers. Other members will be added to the team as necessary. Records cnd materials reviews are in progress to locate the subject flanges and fittings n PNPS. As a parallel action, 29 flanges of the suspect vendors were located in the BECo warehouse system. These have been tested and the test results indicated all but one flange met or exceeded code requirements. The one flange that tested marginally can be justified for use. A data base of all suspect flange / fittings information has been developed and will be mair.tained for tracking purposes. Test procedures for in-situ testing have been developed and test team training has been completed. Racords searches are currently being limited to "0" materials. 8ECo is cooperating with NUMARC's database development. l-
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NRC Bulletin 88-03. *Inadeauate Latch Enaaaement in HFA Tvoe Latchino Relays Manufactured by GEa q , f
. (
- 1. The Bulletin requested the following be performed regarding GE manufactured latching-Type HFA Relays installed or in stock for Class IE (Safety-related) application:
- Identify GE latching Type HFA Relays, Century Series HFA 154, 174, 1518, 171B and Non-Century Series HFA 54, 74, 518 and 718, with manufacturing date code prior to November 1, 1987.
- If the questionable relays are identified, perform the following tests and retain records of inspection and correction actions in accordance with plant procedures for Class IE equipment.
a) In accordance with GE SAL 190.1, measure the distance between the top of the molded contact carrier and top of the relay armature. The distance should be a minimum of 1/32 inch b) In accordance with GE SAL 190.1, perform latching mechanism test to make sure that latching mechanism works c) Repair or Replace any relays which fails the above inspection that
, does not satisfy GE SAL criteria d) All future spare latching type rela,4 must be inspected if manufactured prior to November 1,1987.
- 2. The schedule for completion of Bulletin actions is no later than restart following the next refueling outage scheduled to begin 30 days or more from receipt of Bulletin.
Within 30 davs of comoletion of testing, submit the following information:
- include the number of relays of each type of inspected
- include the number of relays of each type requiring corrective actions for "gap" width of 1/32 inch and
- include the number of relays of each type requiring corrective actions for latching mechanism.
Action Estimated Plan Activity Comoletion Status
- Identify GE Latching type HFA 3/30/88 Complete Relays installed in safety related applications and in stock
- Conduct inspections 8/31/88 Working e Implement corrective actions 8/31/88 Horking
- Transmit response to Bulletin 9/30/88 STATUS 21 Relays in total (7 safety related applications, 10 non-safety related ,
applications, and 4 in stock) Testing has revealed 1 failure (wipe test). i HGL/2324
e. NRC BULLLETIN 85-03 SUPPLEMENT 1: Motor Operated Common Mode failures During Plant Transients Due to Improper Service Settings Descriotion Increase in scope of original bulletin to include testing of all motor operated safety related valves in the previously related systems. (NRC has incorrectly assumed that IST programs would include all valves and also learned that Licensees were not planning to test val <es whose normal position was maintained in accordance with the design-basis events for the plant) NRC has requested Licensees to facto this additional testing into original testing plans. BECo's plan to test at power (need steam to test delta p) has NRC approval.
. Action Estimated Plan Activi ty Comol etion Status ,
- BHROG to provide program with 7/20/88 Complete technical bases for scope of testing
- BHROG to submit program for NRC 7/20/88 Complete l review approval ;
- SECo to determine scope of 8/15/88 Horking testing for PNPS based on BHROG program e Submit scope of testing plans 9/13/88 to NRC
- Conduit testing at power post s.u.
- Submit Final Response to Bulletin post testing ,
detailing results of tests ' STATUS BECo notified NRC in writing on June 1,1988 that BWROG program was being developed and that BECo will evaluate and adopt if appropriate for PNPS. l l u
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*f C ORILLS SCHEDULED FOR 2 NEEK PERIOD OF INTEGRATED ASSESSMENT TEAM INSPECTION (fATI)
AUGUST 8 THROUGH AUGUST 19, 1988
?
Fire Brigade Drills - August 9 5:00 a.m. .
-' August 12 5:00 a.m. ,; August 18 9:00 a.m. ,,
Radiation Protection Orill - August 16 10:/M - 12 Noon Emergency Planning Ort 11s I
- 1) PASS Drill (TSC) August 9 7:30 a.m.
- 2) Contamination Drill (TSC) August 16 7:30 a.m.
- 3) Staff Augmentation Ort 11 (to be determined) i s'
Unannounced Ort 11s 4 h 4 1
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l I RISKISSUESFORRESTART~/!t/ffg Recuired update of the Long Term Plan ITCO
- J Low Voltage on some Buses of the Plant I ctrical pigtribution System under a Particular Operating Mode, su - h > % y ,,fm p .is Control Panel Hiring Jssues Ldent) fled in PCAQs N00 87-23
- 2. and N00 88-02, u t-TO M/G 4* w Licensing Issues Impactilog Appendi RPogramComp)etion.
Jul L% J Potential Replacement of Ep;ess i ik Cc.) -)f.2 p Flow Check Valves on Reactor
- Shk hu;l n Instrument Lines. -/.c u l QtL Potential Inter &ction between 125 Volt DC Buses..-bh gc_g th3 Industry Problems With Rosemount 1153 Transmitters. N=(wh dM-.
r3 Post Work / Start
/UJO -^o r D' est
-- rz_Review d., [5.b ru r' [c r 'e, '
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Sampling Versus 1001. R ceipt Inspe tyn of C mercia u1 y I em . e i. e n r -. n s . , c m -u.w. , ..t 0.C. Circut t Br eaker Testing. r.d Ec t>/ F/J /pg -. ff y q c ., Q Potential Non-conforming Haterials Supplied by Piping Supplies I and West Jersey Manufacturing Company (IEB 88-05). - /. -b /. b.nc. g Evaluation a a c.-n..,.,qLdRepairoJfHp %a ves HO-1001-28A, -288 Yoke Asemblies. -- w1. Instrument Air System Solenold-Opprated Val e Potential Overpressurization. . % % A tym q o., m
LAL 86-10 , Diagnos CAL 86- RFO-7 NRC Ltr Rqs; Mgmt SEP Ltr SALP SALP NRC Restcrtl . Restart 85-99 Team 10 AIT Start Meeting 86-99 Assess From Plan ' inso. PLT Scr Assess 86-41 Plan SECo Rev. O ! E _ E . E _ E _ E . E E _ E E E . g g g/g6- l4/12/861 l 7/86 l 18/27/86l l11/24/84 g- l 7/8/87 l l7/8/87I [7/30/87 I i FEMA '5EP Ltrl EP Ltr BECo "9 PWR Asc Restart Site UtCo - EP Re- w/8EC Prg Plan Self Int to to Work LOOP Nuc Re-Rev _ BECo BECo sponse Submit _ Rev. 1 Stop AIT align l l = l : l : l : l : 18/5/87 l 18/21/871 19/17/87 l l9/17/87 l l9/24/87 l l10/15/8)l l10/26/04 k1/8/87 ] $1/12/87l l 12/87 l 3 E E Public Mtg Start BECo BECo SEP NRC All Re- BECo Self " BECo/NRC Re' on Restart Pre-Sel f Ltr to NRC start Plan A55855- '1 Restart Pilgrim ment Resolution of R/S INPO
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E ' Plan Plan " Ano 7 Task Force Assessment Except DTV Comments to 0*P* R/S Plan Plan Review U2 BECo Cocuner ts I $ ;: M 5 5 l l l = l : l : l : l m Gm lI/4/88 l lI/27/881 l2/18/881 [2/22/88 l l2/22/88l 13/18/c8l l l b/6/88 l l l l l % $$ M U9 ' BECo Decis NRC Comp BECo Self- NRC Resolu- IATI Prep - g BECo on IATI Pwr Ascens Assess /INPO tion of SEP & Comm. E0P SALP m E DTV/SEP Readiness Plan Rev Rpt Results Issues Briefing Issues IATI Str.tus Fini SA R t Addressed
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NRC PUBLIC MEETING c PLfMOUTH, MASSACHUSETTS MAY 11, 1988 w The purpose of tonight's meeting is to provide feedback on the public comments received on the Boston Edison Company's Pilgrim Restart Plan. A summary of all coments received is provided in this handout. The feed- * ' back on these comments is presented in two forms. The majority of the comments received fell into four (4) categories (public participation, Emergency Preparedness, management and containment) and will be responded r 'l to through a transcribed oral presentation. For those specific comments which did not fit into the broad categories, a written response is attached. A report of the meeting will be issued containing the meeting ; transcript and handouts. Also attached to this handout for informction, are the letters to and from Boston Edison Company on the results of NRC review of the Restart Plan and the NRC assessment process milestones. ' f Attachments:
- 1. Agenda
- 2. Summary of Comments Received on Pilgrim Nuclear Power Station Restart Plan
- 3. Written Response to Public Comments !
- 4. i.etters/ Reply to Boston Edison Company Re: Plan Comments i S. NRC Letter to Boston Edison Company Re: Restart Plan
- 6. NRC Assessment Process Milestones i
t i l l 9 /41
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a . ') [ 4 F ATTACHMENT 1 ; AGENDA f May 11, 1988 Public Meeting to Discuss Comments Received on the a Pilgrim Restart Plan ; I Location: Memorial Hall, Court Street, Plymouth, MA F t. Date/ Time: May 11, 1988 - 7:00 - 9:00 p.m.
Participants:
Samuel J. Collins, Deputy Director, Olvision of Rcactor Projects. Region ! Jay M. Gutierrez, Regional Counsel, Region I Ronald R. Bellamy, Chief. Emergency Preparedness and Radiological Protection Branch, Region I J Bruco A. Boger, Assistant Director for Region I Reactors, ; Office of Nuclear Reactor Regulation 1 7:00 - 7:15 p.m. Opening Remarks / Introduction of Speakers S. Collins - Purpose of Meeting ; 7:15 - 7:35 p.m. Public Participation Restart Process J. Gutierrez { [ R. Bellamy ! 7:35 - 7:55 p.m. Radiological Monitoring / Emergency Preparedness I 1' 7:55 - 8:15 p.m. Containment / Safety Enhancement Program B. Boger l S. Collins 8:15 - 8:35 p.m. Management /NRC Assessment Process i l 8:35 - 9:00 p.m. Public Comments NRC Panel ; - \ i 9:00 p.m. Closing Remarks S. Collins j [ 1 I I ! i ! ___ _ w
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d ATTACHMENT 2
, Suraary of Comments Received on the Pilgrim Nuclear Power Station Restart Plan This attachment provides a summary of all comments received during the February 18, 1988 public meeting or by mail concerning the Pilgrim Restart .
Plan. The Attachment also indicates how and where (i.e., oral transcript or written response) the NRC intends to address / respond to these comments.
. The following key identifies the response location:
PP-T - Public Partd:1pation Presentation - Transcript EP-T - Emergency Preparedness / Radiological Monitoring Presen-
, tation - Transcript CONT-T -
Containment Presentation - Transcript MGT-T - Management Presentation - Transcript W - Written Response in Handout 4 5 e
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Summary of Comments The following list summarizes the comments received during the February 18, 1988 public meetings and by mail during the announced comment period. For cross- l reference, the commenters are identified numerically and in general, arranged in order of the afternoon session (oral and written), the evening session (oral and written (W)), and those received by mail (M). The page numbers refer to -
- either the location of the specific comment in the transcript (most cases) or
'. the start of the comenter's presentation. ,
Comenter Pus Response Number Number Comment Location i
. t
- 1. 12 1. Wants Show Cause Hearing to PP-T address:
4
- Management Issues
- Offsite Emergency Preparedness
- Containment Concerns 14 2. NRC does not allow public pp T participation in that only one 2.206 Petition was granted out of hundreds filed 16 3. Restart Plan does not address MGT-T recent management concerns such as contaminated dirt [
pile, fire, and LOOP. i
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s . Attachment 2 - Summary of Comments 2 Commenter Page Response ; Number Number Comment Location l
- 2. 17 1. Wants Adjudicatory Hearing. OP-T 17 2. Problems with containment CONT-T i
. need to be dealt with before .'
Restart. , 17 3. Wants a proven (tested). EP-T workable Evacuation Plan in place prior to Restart. . W 4. The Restart Plan and meeting PP-T transcript should be placed in Manomet Branch of the Plymouth Public Library. W 5. Pilgrim power is not necessary. W
- 3. 20 1. Actual water level in BWR is W not known.
- 22 2. Current valve position W monitoring is inadequate, i
- 4. 23 Opinion - Pro Restart -
l l S. 25 Opinion - Pro Restart - i 6, 27 & Allegation of potential over- W W exposure incident. , i 4 o
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. 1 Attachment 2 - Summary of Comments 3 Commenter Page Response Number Number Comment location
- 7. 33 1. It appears that the reactor is W '
inherently unsafe if a situation
. occurred which puts stress on the reactor.
- 34 2. Wants a tested, workable EP-T i evacuation plan prior to Restart.
1
> 34 & 3. Wants concern over elevated EP-T I M cancer rates resolved prior to
, Restart. I M 4. Can Pilgrim's Containment CONT-T [
4 withstand the stress of a
, moderate to severe accident? -
l , 8. 38 & 1. Management, due to Icrge MGT-T
- W staff changes, is untested l
- in the operational phase of
) Pilgrim, i I 38 & 2. Has restructuring resulted in MGT-T i W overload of VP-Nuclear? i I i= 39 & 3. There is no ef fective emerg- EP-T , W ency plan and specifically there [ are problems of overloaded [ evacuation routes and shelters j for transient population. .l 41 & 4. Wants Adjudicatory Hearing. PP-Y t W l L
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cL. i ..m . .+ O Attachment 2 - Summary of Comments 4 Commenter Page Response Number Wumber Comment Location
- 9. 43 & 1. Have management changes prepared MGT-T W BEco for improved performar.:e?
g 43 & 2. Increase NRC monitoring after MGT-T .
. W startup.
44 & 3. NRC must evaluate containment CONT-T W improvements. 45 & 4. Accer',aoie evacuation plans EP-T j W snould be developed as rapidly as possible, but not
- prereq. for Restart.
i'.
- 10. 50 1. The highest NRC offtetals should PP-T
. make the Restart decision based 1 j upon application of the highest standards of excellence. 51 2. NRC should be extremely alert MGT-T during any beginning phase' of operation. 51 3. Restart should not he allowed EP-T unless adequate emergency response plans are in place.
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. Attachment 2 - Summary of Comments 5
.i Commenter Page Response Number Number Comment Location
- 10. 54 4. NRC h:s to make greater MCT-T (Continued) effor', to explain decisions so that the public can understand them. .
t 55 5. Adequacy of containment must CONT-T be resolved prior to Restart. 11, 56 Opinion - Pro Restart -
- 12. 57 Opinion - Peo Restart -
- 13. 60 1. Repairs and modifications CONT-T (including SEP) completed prior to Restart.
60 2. Management problems resolved MGT-T prior to Restart. 61 3. Upgraded system for monitoring EP-T radioactive emissions from t plant be installed and checked regularly by NRC and State (prior to Restart). 61 4. A workable evacuation plan EP-T be completed prior to Restart. t
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5 e ' ' Attachment 2 - Summary of Coments 6
. Commenter Page Response I Number Number Coment Location
- 13. 61 5. The health impact studies on EP-T (Continued) the communities need to be completed prior to Restart.
; 61 6. A permanent repository for W I spent fuel rods needs to be l . established prior to Restart. -
[ i 61 7. All other alternatives for W f energy production have been { fully exhausted prior to restart. e
- 14. 62 Opinion - Pro Restart. -
Migratory species of fish feed on
- 15. 70 EP-T radioactive substances from {
Pilgrim. t
- 16. 72 Requests Show Cause Hearing. PP-T i
- 17. 74 Who f.ys for the cost of W ;
relocation after an accident? : l
- 18. 75 & 1. Wants Adjudicatory Hearing to PP-T [
W address: l
- Management issues t
- Evacu nion planning l
- Contain. tent problems l .[
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. Attachesnt 2 - Summary of Comments 7
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Commenter Page Response i Number Number Comment Location i
- 18. 76 & 2. Recent(Nov87)piantevents MGT-T i i
(Continued) W indic'te it's unsafe to i Restart. l i
- 19. 78 & W 1. Wants Adjudicatory Hearing. PP-T i 78 & 2. Resolve question on link EP-T l W between cancer and nuclea !
power prior to Restcrt. i i 78 3. Evacuation Plan approvad by EP-T FEMA prior to Restart. 79 4. Commissioners should m4ke MGT-T on-site visits to assess ; health and safety problems. 4 79 5. Wants opportunity to appear MGT-T f before Commission prior to f i Restart. ' i P
- 20. 9 1. Phrases in Plan indicate MGT-T l organization and operation !
in enormous transition. . Which e:tions have been taken? Which are critical ! . to safe plant operation? I i [ i
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- t. i Attachment 2 - Summary of Comments 8 !
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i Commenter Page Responsa l Number Number Comment location ,
- 20. 10 2. Managtment Effectiveness: i
, (Continued)
- Where are the clearly MGT-T specified criteria for ,
," judging?
-
- Where is the performance MGT-T evaluation process
';' defined? 10
- Wno besides BEco top MGT-T management is actually assessing and evaluating
, operation?
I
- Who will do it during MGT-T
! the Power Ascension Program? 10 3. What are the NRC evaluators MGT-T qualifications and experience? l- Wil) NRC be present throughout MGT-T thw Power Ascension process? , Will NRC management performance MGT-T evaluation guidelines be available onsite? i } 'l I r i
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; 1 Commenter Page Response Number Number Comment Location !
- 20. 11 4. Requests NRC presence onsite MGT-T (Continued) through entire process. l (09tage, Power Ascension?) !
- 21. 12 & Wants Adjudicatory Hearing to PP-T W address.
I * ! Management Issues t,
- Reactor Safety Issues j
- Emergency Planning Issues !
I l
- 22. 15 1. Restart Plan is time -
[ dependent, does not reflect I where the process is. ! Specifically: , i M
- Appendix 2, What is the W [
negative float for each f of the activities not l yet completed? [ l t M + Appendix 3 There should W i be 6 shifts of licensed operators prior to Restart. . l M e Appendix 4, All positions W f in the Radiological f Section should be filled .j prior to Restart. l t I t t I
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t 7 At'.achment 2 - Summary of Comments 10 ; Commenter Page Response I Number Number Comment location t
- 22. 15(Continued) i e (Continued) [
M + Appendix 5 The PEI W reports should be updated. - ! M
- Appendix 6, What's the W status of the 11 Open -
Items in the MCIAP? l l l M
- Appendix 7. What is the W !
status of the RAF Items? I l r M
- Appendix 8 What is the W j status of CAL 86-10? [
l M
- Appendix 9, With respect W l to Meeting 86-41, what's f
the status of security, ; fire brigade and i Appendix R7 I 16 2. Comments due 10 days after MGT-T l invitation. [ 17 3. Want hearings on: PP-T e {
- Management Issues l
- Emergency Response Issues !
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t .- : , ;. .'.T !,2 . 1 Attachment 2 - Summary of Comments 11 Commenter Page Response
, Number Number Comment Location 22, 17 4. Public meeting (2/18) falls in MGT-T (Continued) traditional vacation week, Additional time needed to M 5. MGT-T .
review Appendix 11. 23, 19 1. Wants Adjudicatory Hearing. PP-T
- 2. Meeting held during school MGl'-T vacation week.
- 24. 22 1. NRC has yet to demonstrate an MGT-T attitude of understanding fears and concerns of residents.
69 2. Will the NRC allow restart EP-T without being satisfied that evacuation availabilities are adequate?
- 25. 22 & W Opinion - Pro Restart (Technical). -
9 23 1. Health and environmental effects EP-T of operating nuclear plant are negligible. 23 2. Emergency Planning is only a EP-T supple 9ent of engineering safeguards built into the plant. 24 3. Evaciation is possible. EP-T
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! Attachment 2 - Summary of Comments 12
.i a 7 r Commenter Page Response j .j Number Number Comment Location j . i
- 26, 27 Opinion - Pro Restart. - I t.
l
- 27. 28 Opinion - Pro Restart. -
-[
- 28. 29 Opinion - Pro Restart. -
- 29. 30 & W Opinion - Pro Restart. -
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, 31 1. Health records do not support EP-T !
etc.ims of cancer problems. [ t l 32 2. New management has turned MGT-T j around the plant. ! 32 3. Pilgrim energy is needed. W ! 7C 4 Opinion - If cancer registry EP-T data is flawed, the state l government did not do the job I l it was supposed to. t
- 30. 34 & W 1. Disagrees with BECo letter EP-T i that there is a sufficient sheltering capacity for the !
beach population. 36 2. High tide makes evacuation EP-T of Ouxbury beach impossible, j I 37 & W 3. Roads are inadequate for EP-T .f evacuation of area, f I l i,
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Attachment 2 - Sumary of Coments 13 Commenter Page Response Number __ Number Comment Location
- 31. 42 1. Wants Adjudicatory Hearing PP-T for:
- Management Issues -
- Evacuation Plan Issues
- Containment Issues 41 2. Recent plant events reinforce MGT-T views of poor management 73 3. Considering the emergency EP-T planning scenarios, does the spectrum of accident.s include a breach of containment?
- 32. 46 & W 1. Protests meeting forum: MGT-T
- held during vacation waek
- only 10 days notice to review Plan
- discourages public participation by limiting comments to Restart Plan.
- 2. Wants evidentiary hearing for: PP-T
- Contairment Issues
- Offsite Emergency Planning i Issues .
- Health Issues
a .. . . , . . .c .- . c. .' . . . [ Attachment 2 - Summary of Comments 14 r Commenter Page Response l Number Number Comment location 33 49 1. Wants Adjudicatory Hearing to PP-T l address:
- Containment Issues .
- Evacuation Time Estimates
- Management Problems f
W 2. Corporate mission, as stated MGT-T
- in the Restart Plan, indicates safety is second to continued Pilgrim operation.
1 W 3. Restart Plan provides no MGT-T l t criteria by which performance ; will be measured. W 4. There is no sense of what an MGT-T appropriate level of performance is to be for a given task. W 5. Restart Plan calls for greater MGT-T accountability for results, the focus of which sends the l message that the bottom line . is output not as much how its achieved (e.g., safety values). l i I,
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Attachment 2 - Summary of Comments 15
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Commenter Page Response Number Number Comment Location 33(Continued) W 6. Plan calls for anticipating and MGT-T planning for routine work and improvements. It should anticipate and plan for the . non-routine, since it's the unusual or infrequent event that can cause harm. . W 7. It is unclear who is going to MGT-T assess whose performance and how, who will identify, report to whom and correct problems. W 8. Restart Plan states that MGT-T supervisors will be directed to understand the contents of the Plan and will direct the - next line of authority to do likewise. How can anyone be directed to understand? ]. W 9. Infusion of navy-style manage- MGT-T ] ment is apparent throughout the Plan. How will an ^ authoritative paternalistic style of management work with the civilians who have been doing well?
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i. O Attachment 2 - Summary of Comments 16 l' v Commenter Page Response Number Number Comment location 33(Continued)W 10. The reporting structure (navy MGT-T l style, hierarchical authority j structure) is usually not l responsive to complex ' unexpected e' vents. W 11. Reorganization concentrates MGT-T too much decision making at the Senior VP Nuclear position. t i W 12. How does the shift of W ! responsibility for radiological ! q, control to the individual ! supervisors affect the [ necessary attitude change of radiological workers? ! r 1 1 : j W 13. Will the new radiation train- W l [' ing overcome the past indoc- i trination that said the !
"stuff" is harmless?
W 14. Does the fact the new MGT-T . Operations Manager is a former NRC inspector 1 bias the NRC in evaluating i operational readiness? !
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Attachment 2 - Summary of Comments 17 Commenter Page Response Number Number Comment Location 33 (Continued) W 15. Does anyone in the NRC have a MGT-T basis of management expertise from which to evaluate organizational capability . beyond immediate functional levels? W 16. Isn't the reason why the NRC CONT-T denied the 2.206 Petition Hearing request because if policy issues such as Mark I containment design were brought into focus, it would affect other plants besides Pilgrim?
- 34. 51 Requests hearing to address PP-T emergency response plans.
- 35. 53 Several things throughout the W plant are jury rigged.
36, 58 1. Very few citizens have the PP-T time or expertise to go through the testart Plan which therefore limits public participatien.
s e Attachnent 2 - Summary of Comments 18 Commenter Page Response Number Number Comment location 36 (Continued) 58 2. Plan subject to revision, MGT-T ; therefore very little can be accomplished at this stage of restart process. - 58 3. The public has no way of MGT-T knowing how their testimony will be dispositioned.
- 59 4. Future final meeting is MGT-T planned to be held in Washington which is not conducive to public participation.
59 5. NRC has not indicated what MGT-T its criteria or outstanding items are upon which to basing the restart decision and what sort of public participation is planned with l regard to such a list. ,
- 37. 61 Opinion - Pro Restart. -
- 38. 62 1. Opinion - Against restart EP-T (worried about environment).
76 2. Worried about evacuation for EP-T . handicap.
s Attachment 2 - Summary of Comments 19
,' Commenter Page Response Number Number Comment Location 39, 65 1. Emergency Plan needs to be EP-T revised and tested prior to restart.
65 2. The radiation monitoring EP-T (offsite7) is flawed with a lack of (State?) onsite monitoring system. 67 3. Disagrees that thet*'s no EP-T link between cancer ra;e and radiation exposure. 66 4. State's cancer registry EP-T data is flawed.
- 40. 67 Opinion - Pro Restart. -
41, 74 Opinion - Plant should restart for - economic reasons.
- 42. 78 Evacuation of any kind would not IP-T
' be effectively handled due to human element.
- 43. 81 1. Fundamental question of CONT-T integrity of the containment has not been adequately addressed by the NRC. .
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Attachment 2 - Summary of Comments 20 5
; Commenter Page Response Number Number Comment Location 43(Continued)81 2. Wants adjudicatory hearings PP-T (favorable response to 2.206 Petitions).
W 3. Recommendations of the Joint Special Committee Investigating Pilgria:
- Creation of a Commonwealth -
Division of Nuclear Facilities Safety
- Endorsement of compre- W hensive load management and conservation programs
- Prioritize Massachusetts W based electrical generating facilities
- Department of Public W Utilities to estabitsh a five year supply plan without reliance on Ptigris l
r , . Attachme?t 2 - Summary of Comments 21 Commenter Page Response Number Number Comment location 43(Continued)W
- Review of SALP and recommeded measures to correct serious functional deficiencies (and eliminate any Category 3's) -
such as management involve-ment, training, maintenance backlog, staffing vacancies and modification completion - in the areas of: Radiological Protection, W Surveillance, Fire Pro-tection, Security and Safeguards, Assurance of Quality, Plant Equipment, General Management concerns ; and Standby Gas Treatment System Reactor Containment CONT-T Decommissioning Plan W i 1 l i
- Improved Emergency Preparedness EP-T Plan
.u. . - . . .
Attachment 2 - Summary of Comments 22 Commenter Page Response Number Number Comment location
- 44. 87 Homeowner insurance policy has W clause that excludes any damage from nuclear hazard. Some way needs to be found to enable homeowner to insure again:t this hazard.
- 45. 88 1. Sirens and speakers are EP-T unintelligible during tests.
89 2. Emergency planning; concerned EP-T over school, hospital and nursing home evacuation and inadequate road system,
- 46. 92 1. Hanauer eemo or report CONT-T (1971) stated that none of the Mark I containment plants should be allowed to go into oper: 'on. This report was suppressed by the Commission.
S' 2. State health survey statistics EP-T are incomplete. I l l l I
4 , . . ._4 -. Lo o L1 . > l V ; Attachment 2 - Summary of Comments 23 ! r Y b i Commenter Page Response l Number Number Comment location [ 46(Continued)94 3. Spent fuel pool reracking and W l consolidation cause danger of { ?) an explosion, f
.I ^
95 4. The location of an preparation MGT-T : time for Restart Plan public i review was inadequate.
- s 47. 99 1. Emergency Planning
- EP-T l
l 99
- Evacuation plan is terrible [
t 99
- Roads are inadequate j l 100
- Hospitals not capable of j treating radiation victims i L i 101 2. Wants formal hearing. PP-T !
I l 48, 103 1. Emergency planning is EP-T f inadequate for restart, in particular,.the evacuation time estimates and shelter [ i survey, t 104 2. Failure to notify proper MGT-T authorities of the unusual event (fire)eastsdoubts f on the company's integrity.
-l l
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Attachment 2 - Summary of Comments 24 Commenter Page Response Number Number Comment Location 48 (Continued) 104 3. Public meeting was publicity MGT-T campaign on the part of NRC and BECo. 49, 113 Opinion - Pro Restart. -
- 50. W General concern with:
- 1. Evacuation of Cape Cod. EP-T
- 2. Property value after an W accident.
- 3. Embrittlement and corrosion W problems resulting in high repair / replacement costs.
- 4. Nuclear waste. V
- 51. M Opinion - Pro Restart. -
- 52. M Opinion - Pro Restart. -
- 53. M Opposed to resta t untf1 all local EP-T emergency preparedness measures are in place, fully tested and ready for implementation.
. l
- Le r
- Attachment 2 - Summary of Comments 25 l n
Commenter Page Response l Number Nu,m,be r Comment Location 4
- 54. M 1. Wants adjudicatory hearing to PP-T D resolve:
,4
- Management Issues ,
"
- Emergency Preparedness Issues
- Reactor Safety Issues 4 .
. M 2. What action will be taken W against BECo for the two security breaches in
- August 1987.
l 3 .. 2 M 3. What are the results of the W a NRC's review of the overtime [ allegations? il ' i I-M 4. Will the NRC issue a full MGT-T 1 ' report on the events o' November 7 and 8, 1987, including an assessment of
- their causes and suggested 3 remedial actions?
\- M 5. Has the NRC reconsidered W j its procedures for site inspections so that there will be unannounced inspections every twenty-four hour period? . 4 I v-+ --e.,,-w--te-,, ,.--,, _my, , ,,
. . s Attachment 2 - Summary of Comments 26 t Commenter Page Response Number Number Comment location 54 (Continued) M 6. What role, if any, will the W NRC play in the implementation of the LOOP AIT recommendations? M 7. When will the NRC make a CONT-T final decision regarding the installation of the Direct Torus Vent?
- 55. M 1. Critical of NRC for being MGT-T lax with BECo.
1 M 2. Opposed to restart without EP-T a workable evacuation plan.
- 56. M 1. Opposed to restart considering MGT-T continuing problems involving contaminated dirt pile, fire, and LOOP.
M 3. Opposed to restart for EP-T , emergency preparedness issues , including lack of plans, f inadequate roads and lack of shelters.
- 57. M Opinion - Pro Restart. -
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l !' o l? Attachment 2 - Summary of Comments 27 I: y Commenter Page Response Number Number Comment Location
- 58. M Opinion - Pro Restart. -
[ 59. M Against restart in light of past MGT-T [ continuing problems such as contaminsted dirt pile.
- 60. M Opposed to restart because of:
- Incidence of cancer near the EP-T plant.
l
- Inadequate road system for EP-T evacuation.
- No way to dispose of spent W fuel.
- 61. M Generally positive noting -
improvements in plant management and communications with EPZ towns, however, much still to be done in EP-T the areas of evacuation and training of local civil defense
, personnel.
- 62. M Opinion - Opposed to Restart. -
- 63. M Requests Show Cause Hearing. PP-T
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Attachment 2 - Summary of Comments 28 Commenter Page Response Number Number Comment location 64 M Opinion - Opposed to Restart. -
- 65. M Opinion - Pro Restart -
M 1. Pilgrims containment is CONT-T diffferent from Chernobyl M 2. Excess cancer cases, if EP-T observed around Plymouth, could not be attributed to radiation. M 3. Evacuation is possible around EP-T Pilgrim.
- 66. M Strens and speakers unintelligible EP-T l during tests.
- 67. M Opinion - Pro Restart. -
1
- 68. M Opinion - Pro Restart. -
l i M 1. Cites various examples of MGT-T management / policy improvements. l M 2. Cites improvements in EP-T Emergency Planning Procedures / facilities. 5 { l
't Attachment 2 - Summary of Comments 29 Commenter Page Response Number Number Comment location 68 (Continued) M 3. Cites several modifications to - improve reactor / plant quality / safety.
- 69. M Opinion - Opposed to Restart. -
- 70. M Wants Adjudicatory Hearing to PP-T address:
- Management Issues
.
- Emergency Response Plans
- Reactor Safety Concerns
- 71. M Opinion - opposed to restart with M3T-T references to management and EP-T evacuation plan problems.
et ATTACHMENT 3
; WRITTEN RESPONSE TO PUBLIC COMMENTS
!. Comment (s):
17 74 Who pays for the cost of relocation after an accident?
- 44 87 Homeowner insurance policy has clause that excludes any damage from nuclear hazard. Some way needs'to be
' found to enable homeowner to insure against this hazard. 50 W General concern with property value after an accident. Answer: Virtually all property and liability insurance policies issued in the
. United States, except the ones issued by the nuclear insurance pools, exclude nuclear damage. The exclusion means that claims for damage to ,a policyholder's dwelling, automobile or other property by radiation or con-tamination from a nuclear facility would not be collectible under that policyholder's own insurance policies. Thus, if a property owner suffered damage to his property because of a nuclear accident, the compensation would come from nuclear Itability insurance or government indemnity as , provided under Price-Anderson, While the Price-Anderson Act does not pro-hibit private insurers from offering this type of insurance, the standard fire and property policies have contained the exclusion since 1959. The insurers consider that property damage csused by a nuclear accident would be covered by nuclear liability insurance provided under the Price-Anderson Act and that coverage for the same property should be excluded from the conventional homeowner's policy to avoid duplication of coverage.
Attachment 3 - Written Response to 2 Public Comments The Price-Anderson Act, which became law on September 2,1957, as part of the Atomic Energy Act of 1954, was enacted by Congress to meet two basic objectives: (1) To ensure that adequate funds would be available to satisfy liability claims of members of the public in the unlikely event of a very low probability catastrophic nuclear accident; and, , (2) To remove the deterrent to private sector participation in the use of nuclear power presented by the threat of potentially large lia-bility claims if such an accident were to occur. Price-Anderson provides a system to pay funds for claims by members of the public for personnel injury and property damage resulting frem a nuclear accident. Principal obstacles to a claimant's recovery for injuri n or damages under ; the Price-Anderson Act could be the traditional legal defenses against liability available to the defendant, such as the claimant's conduct, , failure to prove the defendants negligence, actions that are the fault of persons indemnified, or charitable or governmental immunity. Congress attempted to remove these obstacles in 1966 by amending Price-Anderson to introduce the concepts of extraordinary nuclear occurrence (ENO) and waiver-of-defenses. "Extraordinary nuclear occurrence" is defined as an l offsite dispersal of nuclear materials in amounts causing radiation levels that NRC determines to be substantial and that NRC determines has resulted, or will probably result in substantial damages to persons or to property of f site. When NRC determines that a nuclear incident is an ENO, then the waiver-of-defenses provisions of the insurance policies and in-demnity agreements making up the Price-Anderson system are activated, re-sulting in an essentially "no f ault" recovery scheme. Claimants would i
7_ _ Attachment 3 - Written Response to 3 Public Comments then need only show (1) personal injury or damat,e, (2) monetary amount of loss, and (3) a verifiable link between the loss and the radioactive mate-rial released. Claimants would not need to establish the fault of any party in order to pursue their claims. For more information, obtain a copy of NUREG/BR-0079 from the Office of State Programs, United States Nuclear Regulatory Commission Washington, D.C. 20555 (301) 492-7000. l l l l f'c. ,
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u.. .. , - , l Attachment 3 - Written Response to 4 f Public Comments . II. Comment (s): j i - 13 61 A permanent repository for spent fuel rods reeds to be established prior to restart. ., 50 W General concern with nuclear waste. 60 M No way to dispose of spant fuel. Answer: 4 The Nuclear Regulatory Commission initiated a rulemaking proceeding on October 25, 1979 to assess generically the degree of assurance that radio-active waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to detemine whether radioactive wastes can be safely stored en-site past the expiration of existing facility licenses until off-site disposal or storage is available. This proceeding became known as the "Waste Confidence Rulemaking." The Commission's decision is summarized in the following findings: (1) The Cornission found reasonable assurance that safe disposal of high level radioactive waste and spent fuel in a mined geologic repository is technically feasible. (2) The Commission found reasonable assurance that one or more mined geologic repositories for commercial high-level radioactive waste and spent fuel will be available by the years 2007-08, and that suffi-cient repository capacity will be available within 30 years beyond l empiration of any reactor operating license to dispose of existing commercial high-level radioactive waste and spent fuel originating in such reactor and generated up to that time, l I I i
r Attachment 3 - Written Response to 5 Public Comments (3) The Commission found reasonable assurance that high-level radioactive waste and spent fuel will be managed in a safe manner until sufff-cient repository capacity is available to assure the safe disposal of all high-levet, radioactive waste and spent fuel. l (4) The Comission found reasonable assurance tha*., if necessary, spent fuel generated in any reactor can be stored safely and without sig-nificant environmental innact for at least 30 years beyond the expir-ation of that reactor's operating license at that reactor's spent fuel storage basin, or at either on-site c.* of f-site independent i spent fuel storage installaticas. (5) The Commission found reasonable assurance that safe independent on-site or of f-site spent fuel storage will be made available if such , storage capacity is needed. i In keeping with its comitment to issue a rule providing procedures for considering environmental effects of extended sn-site storage of spent , fuel in licenstng proceedings, the Comission issued changes to 10 CFR Parts 50 and 51. In adopting changes to 10 CFR 50.54, the Comission established proceJ ires to confirm that there will be adequate lead time for whatever actions may be needed at individual reactor sites to assure that the management of spent fuel following the empiration of the reactor operating license will be accomplished in a safe and environmentally acceptable manner. Accordingly, no discussion of any environmental impart ; of spent fuel storage for the period following empiration of the license ! or amendment applied for, is required in connection with the issuance or amendment of an operating license for a nuclear reactor, i For a more extensive discussion of these rulemakings, see the Federal Register Notice (49 FR 34658 - August 31,1984), i i i l t
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1 Attachment 3 - Written Reeponse to
, 6 j Public Comments <i III. Comment:
J 3 20 Acti.a1 water level in BWR is not known. Answer: .h Reactor vessel level is determined by differential pressure devicSs. Con- [ densing chambers connected to the steam space in the reactor vessel are
. used as the reference. leg. Pressure taps at different levels in the water space o' the reactor vessel are used as variable leg sensing taps for '
narrow anri wide range instruments. The differential pressure method of measuring vessel water level senses the weight of fluid above the lower instrur'nt tap and is calibrated in terms of water at a predetermined density. Therefore, its reading is a collapsed liquid level measurement (the equivalent level of single phase liquid). The reading is thus a representative of the mass of "ater above the sensing tap rather than an indication of the actual fluid surface, which will be higher than indi-
, cated if steam is present in the reactor water.
A more extensive discussion of the response of a generic reactor vessel level detection system to transients can be found in Section 2.17, "Vessel Level Detection" of Appendix A to NUREG-0626, "Generic Evaluation of Feed-water Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term Operating License Applications," Janua ry , 1980. I k I e y.__. - - . _ . - _ . , --. ~ ,._ , ~ ._ ,_ _ _
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l' Attachment 3 - Written Response to 7 Public Comments S IV. Comment (s): 2 W Pilgrim power is not necessary. I 13 61 All other alternatives for energy p oduction have been [- fully exhausted prior to restart. M
,' 29 32 Pilgrim energy is needed.
43 W Endorsement of comprehensive load management and con-servation programs.
.* 43 W Prioritize Zassachusetts based electrical generating , facilities.
43 W Department of <ublic Utilities to establish a five-year supply plan without reliance on Pilgrim. f,he~sso. -@bk Nle The only kaewat requirementsa to addeoe4 the comments given above are con-tained in the Commission requirements for environmental reports found in 10 CFR Part 51. Followin) the granting cf an operating license, the Commission does not evaluate the need for power or use of titernate energy sources in making decisions relatea to operating license for a specific nuclear p'. ant. We do recognize, however, that these issues may be presented and argued in rate cases to the local pub'.ic ctility commissions. e
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l , Atta Ument 3 - Written Response to 8 Public Comments a V. Comment: 54 M Has the NRC reconsidered its procedures for site i inspections so that there will be unannounced inspec-tions every twenty-four hour period?
. Answer: .
At this time, the NRC does not require unannounced inspections every twenty-four hour period. It is our goal that resident inspectors spend their normal werk week at the site with about 20 percent of this time on backshift and/or weekend coverage. These backshift and weekend inspec-tions are generally random and unannounced. Additional inspections are
, conducted by NRC specialists and focused team inspections.
To manage finite NRC inspector resources, including maintaining the flext-bility to respond to events at any site, the inspection program is de-signed to critically examine, on a planned sampling basis, the implementa-tion of the licensee's controls for adequacy in protecting the public. It is emphasized that NRC inspectors are not on-site to duplicate or substi-tute for a licensee's management controls established as a part of its quality verification system. Further, NRC has imposed sufficient event reporting requirements on licensees to assure an appropriate level of at-tention citn be brought to bear on any facility in response to significant events. We believe the current system of routine and random unannounced backshift inspection provides the most effective use of inspector resources to sup-port the NRC's mission and to assure the public's health and safety are protected. g; s g----.--.
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s, .. O l Attachment 3 - Written Response to 9
) Public Comments
. .j - VI. Comment (s): 54 M What a-tion will be taken against Boston Edison Company (BEco) for the two security breaches in August 1987? 54 M What are the results of the NRC's review of the over-time allegations?
. Answer:
NRC's initial review of the security breaches and overtime allegations are documen*,ed in Inspection Report Nos. 50-293/87-30 and 50-293/88-07 respec-tively. Final NRC action is pending ongoing reviews; however, the licen-see's corrective action programt to maintain security barriers and effec-tively control overtime are restart issues and will be reviewed for ade-quacy prior to cny restart decision. i
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. Attachment 3 - Written Response to 10 1 Public Coments VII. Coment:
54 M What role, if any, will the NRC play in the implemen-tation of the Loss of Offsite Power (LOOP) Augmented Inspection Team (AIT) recommendations? Answer: In response to the LOOP at Pilgrim on November 12, 1987, an NRC AIT was dispatched to the site to determine the sequence, the causes and the safety significance of the event. The team's findings are documented in Inspection Report No. 50-293/87-53. The report also contains several recomendations for BEco to consider in order to improve the stations
; ability to respond to isture similar events. All of the recommenditions were added to the NRC's open items list for tracking and subsequent re-view. In addition, four of the recommendations (the third emergency diesel generator, the backup instrument air supply, the additional instru-ments to analyze switchyard transients, and determinatten of the cause of the blcwn fuses in the analog trip system) were made restart issues and will be completed and inspected by the NRC for adequacy prior to any decision on restart.
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. Attachment 3 - Written Response to 11
*i Public Comments VIII Comment:
'7 33 "It appears that the reactor is inherently unsafe if a situation occurred which put stress on the reactor."
Answer:
. All reactor designs are reviewed to determine whether a reactor can with- .. stand, with extra margin, a number of design basis transients and acci-dents. These transients and accidents are identified in the staffs' Standard Review Plan. If the staff should determine that any reactor could not withstand any of the design basis transients or accidents, the staff would require either plant modifications to assure the safety of the reactor or terminate reactor operations.
Presently, the staff is not aware of any design flaws such that the
. Pilgrim reactor would not be able to withstand any of its design basis transients or accidents. The Mark I containment issue will be further discussed in the meeting transcript.
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Attachment 3 - Written Respon.se to 12 Public Comments IX. Comment: 46 4 Spent fuel reracking and consolidation causes danger of an explosion. Answer: At this moment, there is not an application before the staff to expand the spent fuel storage capacity at the Pilgrim plant. Further, thare is no known phenomenon resulting from reracking or consolidation th.it would create an explosion, as suggested. During the course of its review of spent fuel reracking amendments, the staff evaluates design basis trans-f? 1ents and accidents including loss of cooling water and fuel handling accidents to assure that all licensing criteria are satisfied. The oppor- r tunity for public hearing on the modification is also provided. Most (recently, ~the staf f is also evaluating accidents in the pool be considered beyond the plant design basis.fMost notably is r ' tne structural ~ raiiure of the spent fuel pool leading to a subsequent zirconium cladding fire (see NUREG/CR-4982). TheseMn bas 3 events are being studied generically as Generic Issue 82. If determined neces- 'g sary, the resolution of Generic Issue 82 would result in recommendations '/ for improvements at all operating reactors. k! c -
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Attachment 3 - Written Response to 13 Public Comments O. S X. Comment 43 W It is unclear what happens to the plant and storage of radioactive waste when the plant is permanently 3 closed. The questions of the cost involved decommis-sioning, the impact on Plymouth taxes, waste storage, security, and dismantling or "sealing" of the reactor building are of great concern to area residents. The NRC, the State and Boston Edison should develop decom-missioning plans, well before a scheduled closing, to answer these and other questions. Answer: 10 CFR 50.54(bb) requires that no later than five years before the expira-tion of the reactor operating license, licensees of operating nuclear power reactors shall submit written notification to the Commission for its review and preliminary approval of the program by which the licensee in-tends to manage and provide funding for the management of all irradiated fuel at the reactor upon expiration of the reactor operating license until title to the irradiated fuel and possession of the fuel is transferred to the Secretary of Energy for its ultimate disposal in a repository. Final Commission review will be undertaken as part of any proceeding for con-tinued licensing under Part 50 or Part 72. The licensee must demonstrate to NRC that the elected actions will be consistent with NRC requirements
- for licensed possession of irradiated nuclear fuel and that the actions will be implemented on a timely basis.
The issue of spent fuel repositories was previously discussed in Comment
!! response.
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}
XI. Comment: 3 22 Current valve stem position monitoring is inadequate. 2 Answer: l The staffgtion r has been that it is more important to , monitor the variables associated with the' process stream (i.e., water, steam, etc.) rather than concentrate on the accuracy of a given valve a position. Staff reviews routinely emphasize the use of flow rate, temper-ature and pressure instrumentation in order to provide a reasonable means \ to gauge required safety system performance. Once obtained, the process V stream variables can be compared to the design basis values. Plant oper-ators can then make an assessment whether the systems are operating within the plant design basis envelope. 4 e i 1 l e r f l b_
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Attachment 3 - Written Response to 15
'Public Comments XII. Comment:
Allegation of potential radiation 6 27 & W overexposure incident. Answer: s
; Previously, on four separate occasions (twice in 1980, 1982 and 1986), the -
NRC reviewed all documentation supplied by the individual involved as well as the licensee's exposure -records. On each occasion, the NRC concluded that the individual did not receive an exposure in excess of regulatory limits while employed at Ptigrim. In each case, letters were sent to the individual informing him of the results of the NRC reviews. In addition, the issue of whether his exposure at Pilgrim caused any physical ailment was the subject of a three day jury trial in Massachusetts Supervisor Court in 1982 and resalted in a jury verdict in favor of Boston Edison Company. l 4 ) i. b o l
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G g .- .. Attachment 3 - Written Response to 16 Public Comments ,1 XIII Comment (s): 33 W How does the shif t of respcnsibility for radiological control to the individual sJpervisors affect the necessary attitude change of radiological workers? 33 W Will the new radiation training overcome the past indoctrination that said the "stuff" is harmless? - Answer: The NRC is not aware of the training problems noted by the commenter. The NRC routinely (approximately annually) reviews the radiation worker train-ing program for adequacy and documents the findings in publicly available inspection reports. While the NRC is not endorsing the shift of responsibility for radiologi-cal control to the individual srpervisors as the solution to BECo's past problems, we note it is not unc.ommon for supervisors to N nsponsible for worker safety whether .it's industrial or radiological saf ety. Nor-mally, radiological organizations provide the policies, procedures, and oversight of the radiological con .rol program. In placing the responsi-bility for performance on supersisors and workers, they can be held accountable for their actions. Nonetheless, the NRC will expect demonstrated improvement in worker atti-tudes and practices, and will evaluate the effectiveness of radiation worker training, prior to restart. e
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U, . . Attachment 3 - Written Response to 17
. Public Comments i XIV. Coment: "l 50 W General concern with embrittlement and corrosion problems resulting in high repair /replacemsnt costs.
Answer: 1 The NRC currently has programs that require licensees to identify and monitor the condition of reactor system components vulnerable to either intergranuler stress corrosion cracking (IGSCC) or embrittlement. These programs are required to assure that any degradation of components is detected and evaluated. If necessary, plant mcdifications may be required to assure that operation of the plant will be within the previously approved design envelopo. While NRC recognizes that repair / replacement costs for some components may be substantial NRC's primary emphasis and concern is to assure necessary plant modifications restore the plant con-dition to the original design basis so that operation of the plant does not endanger the health and safety of the public.
r , - f,', , p, . .* < < 4 Attachment 3 - Written Response to 18 e Public Comments XV. Comments: 22 M Appendix 2 - What is the negative float for each of the activities' not yet completed?
- 22 M Appendix 5 -
The Performance Excellence Indicator
~
(PEI) reports should be updated. - Answer:
,' The NRC agrees with the comment on updating the PEI reports and has requested Boston Edison Company to formally transmit these reports to the NRC. These will subsequently be placed in the Local Public Document Room (LPOR) for pubite review. In addition, Boston Edison Company will provide an updated PEI report with its Self-Assessment Report / Update of the Restart Plan which will also be placed in the LPOR.
With respect to Appendix 2, "The Target Schedule", at this time all major work is essentially complete and there does not appear to be a need or useful purpose for updating this Apoendix. l L
Attachment 3 - Written Response to 19 Public Comments XVI. Comment (s): 22 15 Restart Plan is time dependent, does not reflect where
' the process is. Specifically:
M
- Appendix 3 - There should be 6 shifts of licensed operators prior to Restart.
65
.~. I
. M
- Appendix 4 - All positions in the Radiological
; Section should be filled prior to hstart.
M
- Appendix 6 - What's the status of the 11 Open Items in the MCIAP?-
t M
- Appendix 7 - What is the status of the RAP Items?
M + Appendix 8 - What is the status of the Confirma-tory Action Letter (CAL) 86-107 M
- Appendix 9 -
With respect to Meeting 86-41, what's the status of security, fire brigade and Appendix R7 f 35 53 Several things throughout the plant are jury rigged. ! 43 W Review of SALP and recommended measures to correct serious functional deficiencies (and eliminate any I Category 3's) such as management involvement, train-ing, maintenance backlog, staffing vacancies and modification completion in the areas of: Radiolcgical Protection; Surveillance; Fire Protection; Security l and Safeguards; Assurance of Quality; Plant Equipment; General Management concerns and Standby Gas Treatment . System.
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a i Attachment 3 - Written Response to 20 , Public Corments ;
. Answer:
- , The NRC agrees with many of the comments and recommendations noted above by commenters 22 and 43. The majority of these issues have been pre-vtously identified by the NRC and are well documented in Inspection Reports, Systematic Assessment of Licensee Performance (SALP) Reports, and l
generic documents such as NRC Bulletins and Information Notices. Simi-larly, the majority of these issues have been identified as restart items [) [
. and have been or will be inspected by the NRC to verify adequacy. This
( includes issues such as: the Standby Gas Treatment System single failure , concerns; the staffing vacancies; the Appendix R modifications; the main- ' tenance backlog; and the effectiveness / adequacy of the radiological and l security prograns. " i Finally, it should be noted that the NRC plans to perform a 1 d SALP, and conduct a Integrated Assessment Team Inspection to evaluate the effective-ness of licensee corr:ctive action programs and the readiness of the plant - equipment and personnel to resume power operation, prior to making any decision on restart. . I l 2 i i l l i I l .! a i .I
~ ' ' QAff CONVERSATION RECORD ) flMC/O.soe ,5; 4 V rf I
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$4GNATURE A O SE OW.S. 4.P.O. 1983 80t 186/0886 l
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q . OFFICE MEMORANDUM j Boston Edison Company dY.W+ +N
- To: Mr. R.G. Bird From: Mr. R.N. Swanson Record Type A4.08 Date: June 3, 1988 Dept. Doc. NED 88-335 Non-Safety Related
Subject:
Issues That Could Potentially Delay Restart - Revision 15 Distribution: 1 E. Kraft R.V. Fairbank R.A. Ledgett J.E. Howard
, D.J. Cronin P.T. Antonopoulos H.V. 0 helm MED GL's F. Famularl R.E. Grazio E. Ziemianski A.V. Moitsi R. Anderson K. Highfill L. MacDonald R.E. Sherry
,J. Flannagan N. Brossee W.H. Deacon
' This memo transmits Revision 15 of the listing of issues that could potentia 11y delay restart.
One issue has progressed to where it is no longer a significant risk to delay plant restart. The issue, "ATHOS Division II Root Cause Determinations", will be deleted from subsequent report revisions. Two emergent issues have been added to this revision of the report. These are:
- OC Circuit Breaker Testing.
- Potential Non-conforming Materials Supplied by Piping Supplies Inc.
and Hest Jersey Manufacturing Company (IEB 88-05). These issues will be updated untti they no longer present a significant risk to delay plant restart. Changes to the presentation from the previous revision have been noted with a ch nge bar and triangle in the right-hand margin adjacent to the change. We are continuing to expedite completion of these items to minimize impact. Reports will continue on a weekly basis. RNS/HV0/emq R E5 E[V E D .m ELFASFO m mamer 212 ( [(' NW8 IOR USE 1 t umod
- 1 f/43.
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, RISK ISSUES FOR RESTART
- l j
Required update of the Long Term Plan Documentation of normal and emergency AC distribution system bus
', loading and load flow Control Panel Hiring Issues Identified in PCAQs N00 87-23 j and N00 88-02.
Licensing Issues Impacting Appendix R Program Completion I; b
*f 7"
Potential Replacement of Excess Flow Check Valves on Reactor Instrumentation Lines. Potential Interaction between 125 Volt DC Buses. ATHOS.Olvision II Root Cause Determination. 4
- Industry Problems With Rosemount 1153 Transmitters.
Post Work /Startup Test Review. . Sampling Versus 1001 Receipt Inspection of Commercial Quality Items. D.C. Circuit Breaker Testing. Potential Non-conforming Haterials Supplied by Piping Supplies, Inc. 2$5 and Hest Jersey Manufacturing Company (IEB 88-05) 6 i l
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.. 'A ISSUE Required Update of the Long Term Plan.
It is a requirement of the PNPS license to submit semi-annual PROBLEM
, updates of the Long Ters-Plan (LTP) to the NRC. The most t recent submitted update was March 1986. The LTP must be ~
updated and submitted to the NRC to ensure license compliance. SCOPE Update the LTP information (NRC commitments, PDC packages, SJA's, WSP's, etc.) :nd prepare a NRC submittal. H0H DISCOVERED BECo. commitment tracking and NRC Salp Report.
~
RECOHHENDEO R ESOLUTION -- Update the LTP, submit for internal approval, and transmit to the NRC. For the long term, develop a system to provide automatic LTP updates. Estimated Action Comoletion 511121 ACTION PLAN
- Update LTP 7/01/88 In Progress
-
- Submit LTP to the NRC. 30 days following receipt of an approved LTP RESPONSIBILITY NUORG (Planning & Produce an approved LTP Outage Management)
NED - RA&P Transmit LTP to the NRC STATUS LTP revision is targeted for 7/01/88. Once approved, the LTP will be submitted to the NRC. Assuming a timely LTP update, this item should be a low risk to delay restart. e f 6 l 4 n- , , , . - - - . - - - - - , . , -
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RESPONSIBILITY: NED - Electrical & RA&P ;
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STATUS Negotiations with RENVEC have been completed and were successful in raising the guaranteed minimum offsite power source voltage. PDC 88-07 is complete but is being revised to incorporate a change requested by the ORC. ; A review of the contractor-produced plant voltage study by BECo personnel found an error in the study caused by the omission of vendor-specific data into the study. The error resulted in predicting hi actually be experiencedi.e., (gher MCC actual busvoltage MCC voltages willthen be will lower then originally calculated). To resolve this problem, NED has investigated alternatives to minimize cost and schedule impact. Relocating some non-safety related loads from safety-related MCCs to non-safety related MCCs will be necessary to improve voltage on the affected buses. g The technical specification change for the degraded grid voltage relay setpoint change is prepared and is being finalized. NRC subalttal of the requested change to BECo is a t critical part of this issue. Based on the remaining work, newly discovered study error, and turnaround on the Tech Spec submittal, this issue is
' characterized as a moderate-to-high risk to delay plant restart.
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L ; , . . s e N. Contr31 Panel tiring issues identified in PCAQs N00 87-23 and liiUE N00 88-02. PROBLEM During the program to verify the connection adequacy of panel terminal board screws, N00 identified approximately 2203
~ ' wiring problems in control panels for resolution via PCAQs N00-87-23 (07-11-87) AND N00 88-02 (01-06-88). These wiring problems include: .4
- Three wire terminations
- Bent lugs
- Broken terminal board barriers
- Hire exposed beyond barrel of lug PCAQ N00 87-23 had 1273 concerns that were addressed by a NED walkdown with the resolution of the concerns documented in PCAQs NED 87-149 through NED 87-181 (9/30/87) and sent to N00 for resolution on 10/1/87. These PCAQs contain approximately .
; 500 items requiring repair or rework. On 11/30/87, the PNPS Work Scope Review Comittee requested NED's assistance in resolving these PCAQs.
PCAQ N00 88-02 had 975 concerns that need to be walked down and analyzed by NED and sent to N00 for final resolution. iCQEE Identify and resolve start-up issues from approximately 2200 , wiring problems identified in PCAQs N00 87-23 and 88-02. l RECCNHENDED l SOLUTION NED will evaluate all items identified by PCAQs N00 87-23 and N00 88-02, identify start-up items, and provide resolution of the items as it is determined. All identified safety-related termination problems shall be resolved prior to restart. A post restart, longer ters
- program will be incorporated to resolve non-safety related termination problems.
ACTION DATE DUE STATUS ACTION ELji Provide NED Resolution of all items 10/1/87 Complete in PCAQ N00 87-23 ,
- Issue PDC 87-80 to repatr/ Complete
! 1/15/88 rework cable terminations , L Halkdown PCAQ #N00 87-23 safety-related 1/22/88 Complete r terminations l
!ssue FRN/ hrs for safety-related items in 1/29/88 Complete Control room / Cable Sprcading Room
- Complete Halkdown PCAQ #N00 88-02 safety-related 1/22/88
. terminations
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- Issue FRN/MRs for safety-related items in EL&M 1/29/88 Complete
'e panels outside Control Room / Cable V Spreading Room . Perform work to correct problems found with safety-related terminations 06/10/88 Horking - lg@g delays due to operational availability RESPONSIBILITY NED-Power Systems STATUS Final construction completion has been delayed due to operational release of equipment for work. There are currently 3 outstanding
., maintenance requests out of a total of 67. A new maintenance request was added to the work scope. Of these, 19 conductors need retermination.
A question has been raised regarding functional testing of circuits reworked as part of this issue. A task force is investigating methods to demonstrate circuit function. Preliminary indication is that while the E-203 acceptance criteria was adequate, existing surveillance procedures shall be performed for most repairs made during this project. Functional testing will be performed for future work. Functional testing will not be performed on completed repairs unless discrepancies are found furing surveillance testing.
- The risk for this issue to delay restart is low assuming equipment A can be made available by Operations for construction work. m 9
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liSUI Licensing Issues Impacting Appendix R Program Completion PROBLEM The following licensing issues need resolution to complete Appendix R I closecut. Many of the issues ha've BEco action complete with resolution dependent upon NRC action. The issues will be reported
, untti each is closed within the NRC. These issues are taken from the weekly Appendix R project report.
ISSUE ACTION DATE DUE i NRC SER on Exemption Request 11, 12, 13 MRC 06/15/88 14, 15, 18 and 22. (TAC # 53416,65962) ; Fire barrier deviations reconciled by BECo submittal to 06/30/88 t$h l engineertug evaluation using the NRC NRC needed to clarify Generic Letter 86-10 process, the SER related to License Amendment 35 Issues will be driven to resolution by the responsible party and project !
, management. Status will be maintained for NRC actions. ,
RISK: BECo licensing submittals have been complcted to support restart. The NRC has provided target dates for replies to 8ECo. There are no known outstanding questions for BECo to answer on these issues. This a s issue is recharacterized as a low risk to delay restart due to increased responsiveness by the NRC.
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m: ' runnuai avkiacement'or txcess eiortneci vaives on neat; tor - ~ Instrumentation Lines. . i - PROBLEM: During leak rate testing performed under PNPS Procedure 3.M.3-2, some excess flow check valves exhibited excessive leakage. The plant does c: not have sufficient spare parts to repair the valves and the valve manufacturer (Chemequip Company) reo longer supplies equipment to an approved quality assurance plan. Valve repair or replacement will likcly be needed prior to restart. If the valves are replaced with another manufacturer's valve, replacement time could take 8 to 12 weeks. Valve replacement using valves from the original manufacturer, Chemequip, has been investigated and resulted in a lack of documentation with the plant designer, Bechtel, supporting either code certification or structural evaluation of the existing valves. In addition, the body of the Chemequip valves has a section with a reduced cross-section approximately equal to that of a 1/2" pipe. fince the excess flow check valves are used in 1" piping, the valve b3dy is a weak component. This is contrary to code requirements. Two excess flow check valves were replaced in PDC 85-07 with an alternate manufacturer, Dragon Valves. Pipe flow restrictions in the L' piping to these valves prevent sufficient flow to permit testing of the valves. These valves may have to be replaced. SCQM: Approximately 10 excess flow check valves have exhibited leakage. They are in the following systems. Jet Pump Piping RCIC Steam Line d Recirculation Pump Risers Core Spray Plenum Reactor Water Level Piping Recirculation Pump Seal Cavity . Two Dragon Valves on the reactor water level instrument lines cannot be tested due to piping flow restrictions preventing sufficient actuation flow. There are a total of 51 excess flow check valves on reactor instrumentation lines, and there is a cotential all may have to be reolaced. HCH QISCOVERED: Leakage was found in leak rate testing while performing PHPS Procedure 8.H.3-2. NED was notified by telecon on 3/10/88. While attempting to locate parts or spare valves to perform repairs, problems with qualification documentation were discovered. RECCMMENDED ESQLUTION: The station will clean the valves and retest. NED will attempt to locate valve parts from other utilities. As parallel actions, NED l
(CONTINUED)
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I 1 will perform an equivalency evaluation to find an alternate supplier and NED/QA will review the existing manufacturer's QA program to determine if the manufacturer can supply valves that will meet BECo's
. quality standards. If station rework and testing results in excessive leakage, new valve procurement and replacement will be recommended.
NED will evaluate the structural acceptability of the existing Chemequip valves to justify coltinued usage of the valves that passed the leak rate test. A purchasa order for 12 replacement Dragon valves in being issued. Additional valves will be ordered basei on the results of the NED evaluation. 4 NED will also evaluate the excess flow check valve test criteria and recomend an inservice test program. ACTION PLAN FORECASTED
., ACTION COMPLETION STATUS Perform qualification test on 06/15/88 Horking Chemequip Valves (Burst Test)
Perform seismic analysis if 06/15/88 Horking qualification test is successful Based on seismic analyses Ldd 07/15/88 Start pipe supports 06/15/88 g
- Complete -
Issue P.O. for 12 Dragon replacement 05/25/88 valves (to replace leaking valves) Delivery with authorization to procure expected material for 52 valves (if 07/15/88 ! qualification test is unsuccessful) Issue P.O. to Chemequip to procure 05/27/88 Complete internals for 12 valves to repair leaking valves in the event qualification testing and seismic analysis is successful
- Install Dragon Valves or repair (Later)
Chemequip Valves, as appropriate l Develop PDC to install Dragon Valves. 07/15/88 Start if necessary 06/15/88 RSPONSIBILITY: NEO - FS&HC I&C SIAIl$: Preliminary structural evaluation of the existing Chemequip Valves shows the valve is marginal for pressure rating and cannot withstand ( significant mechanical loads. Specification H-561 has been issued l for the replacement Dragon Valves and a purchase order is in progress. ! This issue is re-characterized as a high risk to delay restart due to I the potential for the scope to expand. i
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I PROBLEM: Plant design criteria specifies separated, redundant sources Cf DC power that can withstand the failure or loss of a single component without the loss of systems necessary to safely shutdown the plant. During the root cause investigation of an ATHOS, Division II trip u signal, testing performed as part of the investigation revealed a potential interaction between the plant redundant 125 Volt DC divisions. The interaction identified was a corresponding voltage transient on the redundant 125 Volt DC systems when a single Recirculation Dump H-G Set was started. The transient was duplicated for the start of either M-G set. Investigation of the problem and
- resolution, if necessary, will be restart items.
510 5 : Potential interaction ' cross-connection) of the redundant 125 Volt DC divisions. The potential cross-connection appears to be caused by input voltage fluctuations to the battery chargers caused by starting large motors (4500 hp and larger) on the 4160 volt buses. H0H DISCOVERED: During testing as part of the root cause investigation for an ATHOS, Division II trip signal. RECOMMENDED RESOLUTION: Perform a design review and testing, as necessary, to determine if
- there is a DC system interaction. Based on the results of the review and testing, perform additional investigation and testing to find the interaction cause. Implement the appropriate changes to eliminate DC system interaction.
ACTION Estimated PLAN . ArttLLty Comoletion STAT 1)$ e Perform design review, as necessary, 4/15/88 Complete to determine if there is DC system cross-connection.
- Prepare test procedure 6/10/88 Procedure drafted e Perform field test 6/17/88 Horking e Analyze any regulatory teplications Based on and take appropriate action. test results e Develop and implement engineering Based on action to eliminate any interconnections. test results ESFdSIMkill:
NEO - Power Systems, SLSA, and !&C. l l L
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- STATUS: Ossign review indicates the independent D.C. divisions are not 'j interconnected v1 the Recirculation MG set circuitry. Testing is a being planned and coordinated with the Plant Systems Group to determine the exact cause of corresponding voltage transients. The test procedure has been trafted and issued for comment. Test equipment is being selected and scheduled to support a 6/17/88 test.
This issue has a low risk to delay plant restart. g F 8 C s
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'ISSUI: ATHOS Division II Root Cause Determination.
PROBLEM: On 02/03/88, a Recirculuion Pump Trip (RPT) and alterriate Rod *
.- Infertion (ARI) trip signal was generated unexpectedly from the .; Anticipated Transient without Scram (ATHOS) Division II circuitry.
j The root cause(s) of the event is under investigation. SCQPP.I: ATHOS circuitry, inputs to the circuitry, and electrical power supplies to the circuitry.
, HOW DISCOVERED:
i The ATHOS Division II trip was annuaciated y the control room along with the RPT and ARI. The Recirculation P Wps that were in operation at the time tripped and the Rod Position Information System (RPIS) indicated tetivation of the ARI signals The event occurred during the perta of time in which post modifictalon testing of PDC's 86-102 (ATHOS Reactor Feed Pump trip) ant 87-30 (AT E Pad culation Pump Drive Motor 8reaker Trip) was ongoing. RECOMMENDED RE56LUTION!
.i Subsequent to the ATN05 inadvertent trip, a root cause investigation team was assembled and an action plan developed for data collectivn and testing of the ATN05 panels and associated circuitry. The team will provide racomendations to prevent recurrence.
. ACTION Estimated PLAN A-tivity comoletion STATUS
- Perform root cause investigation. 04/01/88 Complete
- Independent review of root cause 04/15/88 Complete investigation.
05/20/88 Working b
. Issue recomendations.
- Install FRN to resolve potential 05/27/88 grounding problem.
- Complete PDC 86-102 and 87-30 post 06/03/88 aodification testing.
BI5f0MIBILITY: NED - S&SA, and !&C. SIAIUS: The root cause investi:ation and independent review are complete. A definitive root cause could not be determined; rather, potential root causes were identified in the areas of ground;ng scheme errors, voltage transients, loose connections, and/or an inspection error. Specific problems (grounding and loose :ennections) were checked and corrected as necessary. This issue is no longer a risk to delay ' plant restart and will be deltsed from future revisions of this report.
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.l ROBLEM: The following industry problems have been identified tith Rosemount 1153 transsitterst J e The Rosemount 115* transmitter has a fast response and can
, respond to systee "noise" perturbations. When usid in certain i applications (e.g., main steam line flow, reactor water level, e differential pressure applications), sensitivity to system noisa can result in unwanted safety system actuations. Main Steam t.ino Flow is believed to be the application Jf greatest susceptibility
, at PHPSs e Some transmitters have experienced failures ca'Jsed by impurities ;
in the diaphragm sensing module. The failures result in the transmitter shifting off scale either high or low without an input change. Failures have been random but all necurred within the first year of operation. l
- Tallures have also occurred due to leakage of the silicon fill .
inside the diaphragm sensing module. This f Ailure results in a sluggish or drifting response and has occureed after the transmitter has been operated for a period af time. Pilgrim has Rosemount 1153 transmitters insta', led in several
. applications.
SCOPE: Rosemount 1153 t ansmitters installed by the Analog Trip System l modification M 64-70. There were approximately 56 transmitters i installed. HOW Q15 COVERED: ; l The problems are industry-related problems reported in GE SR 463 and r notification from Rosercynt by letter dated 12/15/86. NED performed a telephonk survey on 04/07/88. RECOMMNDED Rf10Lui10N: Ieylement SIL 453 reconnendations to monitor transmitter outputs for noise. GETARS will be used to obtain data. The data will be anat> zed by spectral analysis. Daily surveillances per procedure 2.1.15 will be performed to detect malfunction caused by impurities or silicon leakage from the diaphragm sensing mohle. Procure 16 spare transmitters to be used to replace any trah..attters that are susceptible to process noise. Response tice testing will be performed on &ny problem transmitters to determine the variable i damping setting. ACTION Estimated PLAN Activity Comoletion STATUS
- Procure response time test equipment 06/20/88 P.O. to b issued
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06/03/88 I e Procure Rosemount Transmitters with 10/04/88 P.O. to be damping, delivery issued 06/10/88
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* !ssue FRN to install spare transmitters 10/14/88 h for transmitters with noise- l 0 susceptibility.
i e Develop PDC to connect transmitters 06/20/88 SJ/. to GETARS. Complete /$1 ; i e Procure needed GETAR peripheral equipm*r.t. 06/17/88 Scoping
- Conduct training for PNPS staff on 06/24/58 operation of response time testing.
. RESPONSIBILITY:
NED - IbC. . 4 STATUS: Scope of activity is defined and capital authorization is in preparation. Rosemount is quoting a 16 week delivery for spare transmitters. Some expediting can be expected. This is considered a low risk to delay restart since the spare transmitters will not be s$1 needed untti the power ascension program is underway. O 4 k t i i i l J l
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y . . , - .. . .l , . . . 1MUI: Post Work / Start-up Test Rvview PROBLEM: Due to the nJober of plant design changes and maintenance tasks performed during RF0#7, a review of post work testing performed and planned start-up testing is being conducted to demonstrate the 4 changes and maintenance work have not altered the plant dynamic response. The review will include changes or major maintenance work that could have altered the plant dynamic transient response since the last successful response to a transient. The review will identify any additional testing or plant instrumentation needed prior to restart to demonstrate adequate plant transient response. iCQPI: RWiew of post work testing for 15 RF0#7 PDC's and 12 major maintenance tasks. Also review plant design changes to affected systems implemented after the last known successful dynamic response to a plant transient (transients developed using FSAR Chapter 14 Table 14.4-1). , H0H DISCOVERED: Resulted from an extended, enhanced design review board review of RF0#7 modtf1 cations. RECOMMENDED RESOLUTION: Perform a review of post work testing performed for identified PDC's and maintenance tasks. Review plant transient response history and PDC's performed on the affected systems since the last successful transient response. Provide recomendations for any additional startup testing or plant instrumentation, if needed. ACTION Estimated PLAN Attivity Comoittien STATUS
- Develop work instruction for post work 05/23/88 Complete test review.
- Assemble test documentation and review 05/31/88 Horking test ;
- Identify last successful plant transient 05/12/88 Complete
! responses.
- Collect, analyze, and document transient 05/27/88 A responses, m
- Identify PDC's since last successful 05/31/88 transient.
- DRB review results of each activity above 05/31/88 and provide recommendations to NED Hanager for any start-up plan changes.
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- . o Prepare recommendations for any 06/10/88 F, additional testing or instrumentation.
- 5 RES M SIBILITY:
4 NED - Risk & Reliability. 51ATUS: The post work test review werk instruction has been issued. Other
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upcoming scheduled tasks are in progress. This is considered a medium risk to delay restart. 9 t e
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l ,. 11521: Samp1tng Versus 1001 Receipt Inspection of Comercial Quality Items. PROBLEM Receipt inspections performed on certain commercial quality iters (CQI's) by 8echtel, acting as SEco's agent, were performed on a
- sampling basis instead of the specified 1001 basis. This resulted in L the installation of some equipment (e.g., drywell spray nozzles) that was inconsistent with design requirements and led to NRC Violation
- 87-45-02. A concern has been raised over the potential installation of other equipment not consistent with design requirements that was sample inspected upon receipt. The risk is that equipment , inconsistent with design specifications could be installed in the plant.
SCOEI: Quality Control investigations indicate 487 receipt inspections were made using sa.mpling as opposed to the specified 100% inspection. HOW DISCOVERED: , h During a Quality Control surveillance inspection of the drywell spray , 11 nozzles.
- RECOMMENDED I RESOLUTION
3 Review the 487 items that were sample receipt inspected for adequacy and document the results of the review. Initiate any corrective actions, if necessary, to replace equipment found to be inadequate. Review and revise any process controls to ensure the problem will not recur. ACTION Estimated . PLAN Activity Comolation STATUS e Review 487 CQI receipt inspections. 08/01/88 29% A Complete ZE
- Correct process issues. 08/01/88 25%
Complete STATUS: Approximately 29% of the 487 CQI sampled receipt inspections have been reviewed and dispositioned as acceptable for use with no follow-on action. Due to the number of reviews to be conducted, this issue is characterized as a moderate risk to delay restart.
Ulull DC' Circuit B'rea r Testing.
. PROBLEM: DC circuit breakers at PNPS have not been tested to demonstrate !
operability. DC breaker testing surfaced as an issue in a violation '
,' from the February, 1988 Electrical System !
resulting inspection/ audit. Ten of 39 DC motor control center breakers were imediately tested and all passed trip / fault tests. There are a total of 124 automatic DC breakers at PNPS, and further testing is at risk due to the unavailability of sr .*e breakers of the sizes and types in the plant. Breaker unavat tbility is aggravated by the age of the PNPS breaker; most types are no longer manufactured and available replacements would not likely fit into the PNPS panels. NED is developing a test plan and basis in conjunction with Station Maintenance to test a portion of the 124 breakers prior to restart
, with the balance to be tested post restart. The NRC is monitoring BECo's action.
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iCQEE: 124 DC breakers will have to be tested. A plan and basis will be developed to limit the scope to a reduced number to be tested prior to restart. The plan is as follows. l '
- 10 (of 39) breakers already successfully tested on MCC's 07, 08, and 09.
a e 29 additional breakers to be tested prior to restart
- 4 (of 5) on D16
- 4 (of 5) on D17
- 6 (of 6) on 010
_._ H (of 39) additional on MCC's D7, 08, and 09 29 Total d A basis is being developed to defer testing on panels D4, D5, 06, Di9, 036, and 037 to post restart due to the low probability of a breaker failure in these panels degrading the DC system. Breakers failing the testing would be reason to expand the pre-restart test scope. HOW DISCOVERED: Surfaced as an issue and violation from the February, 1988 NRC Electrical System inspection / audit. RECOMMENDED RESOLUTION: NED is providing test acceptance criteria and has developed a test plan to test a portion of the DC breakers prior to restart (resolve the violation) with the balance of testing being conducted af ter restart. The plan includes a basis to defer testing some of the breakers until post-restart. NED is contacting component manufacturers to find replacement breakers. Station Maintenance is attempting to locate spare breakers from other utilities. Schedules are being developed to test the limited breakers for which spares are on-site.
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! (CONTINUED) "i ACTION Estimated ;, PLAN _ Activity comoletion STATUS Provide test & acceptance criteria s N/A Complete for DC breakers
- Provide supporting justification for the 06/03/88
, test plan e Investigate replacement breakers with N/A Complete manufacturers
- Provide procurement requirements to 06/06/88 Horking Maintenance e Maintenance to investigate spare procurement On-going, from other utilities Maintenance
.- Activity 4
- Maintenance to schedule testing for limited (Later)
- breakers for which spares are on-site R[SPONSIBILITY: b NED - Electrical, Plant Maintenance.
STATUS: In response to the violation for lack of DC circuit breakers testing, testing was parformed successfully on 10 DC MCC breakers for which spares were available on-site. Investigations into obtaining spare or replacement breakers from manufactures have resulted in lead times for delivery in the order of 20 weeks. Due to the age of the breakers, some types are no longer manufactured and replacements cannot readily be obtained. Plant Maintenance has surveyed other utilities for spares and has been unable to obtain any. Based on these circumstances NED is developing a test plan with supporting justification and acceptance criteria to test a portion of the DC breakers prior to restart with the balance to be tested ,
- post-restart. The NRC is following BECo's progress on this issue and is interested in reviewing the test plan.
Due to the long lead time to obtain spare or replacement breakers and i the risks associated with testing without spares, this issue is ' characterized as a high risk to delay plant restart. l t l , l l l [
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.- Potential Non-ConforCing Materials SuppIled by Piping Supplies, Inc.
and West Jersey Manufacturing Company (IE8 88-05). ER0!LLIM:
- Piping subassemblies supplied by Piping Supplies Inc. (PSI) and West Jersey Manufacturing Company (HJM) to various use,rs have questionable ., Certified Haterial Test Reports (CMTR) that were used to certify that foreign comercial grade carbon and stainless steel compiles with the requirements of ASHE Section III, sub-article NCA 3800, or ASTH.
These potentially non-conforming subassemblies (ptpe fittings and flanges) may have been used in safety-related applications. Materials from HJM or PSI may have been supplied to a user from another company to which HJM or PS! was a sub-supplier. This information was furnished to the industry by NRC I&E Bulletin 88-05. The Bulletin requires utilities to identify potential non-conforming material in both safety and non-safety related applications and take corrective action. Corrective action may include demonstration the . material compiles with code requirements, justification for continued operation, or replacement of the material. K0EI: Review of material records (Chill, HRR, and HRIR) to identify any potentially non-conforming material. Corrective action (unknown I. scope) for any identified material from the subject suppliers. HOW QISCOVERED: NRC Bulletin 88-05. RECOMMENDED RESOLUTION: _ b Perform a review of the appropriate material records (CMTR, HRR, and HRIR) to identify any potentially non-conforming material. Evaluate any discrepancies and resolve any non-conforming material through analysis, material replacement, or other appropriate. action. ACTION PLAN Activity Estimated comeletion STATUS Identify the appropriate caterial records 06/10/88 Horking H to search i e Review records to identify applications 06/28/88 Horking where subject material was used
- Evaluate and document applications to i Based on determine appropriate disposition of records discrepancies review o Respond to Bulletin 09/13/88 Institute follow-on actions to resolve l problems as determined in dispositions l
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(CONTINUED)
) RI1PONSIBILITY: ' i NED - RA&P: Overall coordination and Bulletin response.
(NED - FS&MC) Records review and disposition of discrepancies (QA ) (Records Management) NED - FS&HC: Follow-on resolution of problems. 11&Ius: A scoping meeting was conducted on 05/18/88 with the appropriate organizations to organize the effort to respond to the Bulletin. A A strategy to sort and review records was developed and is being G* refined. Approximately 11,800 records were identified for review. - Preliminary information has been received for material procurred by Bechtel. MED evaluation of the Bechtel information is in progress. Based on information from the NRC, emphasis will be placed on flanges and similar sub-components. 8ECo has also approached the BHROG to possibly address the Bulletin generically. Due to uncertainties in the amount of material in Pilgrim, this issue is characterized as a high risk to potentially delay restart. N e I 1 1 - 1 l f i i
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RALPH G. BIRD Gf Ji
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KENN ETH L. HIGHFILLh '$dfffY lWVP'* STATION DIRECTOR 1, ROY A. ANDERSON PLANT MANAGER . RONALD A. VARLEY MANAGER, EMERGENCY PREPAREDNESS e
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- DECONTAMINATION 20070 i -
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PILGRIM STATION NON - BOSTON EDISON RAMP DOWN 2000-M A 1600-N - p 1200-l O 800- T I W . k\ 0 ; ; ;; ; ; ; . ; ; Sep- Nov- Jan- Mar- May- Jul- Sep- Nov-
; 87 87 88 88 88 88 88 88 E FRCST G ACTUALS -*- GUARD FRCST + GUARD ACTUALS a - - . , - . _ . , - - - - v-- - - - --
Open Temp Mods ] 90 l 1/87 2/87 3/87 4/87 5/67 6/87 7/87 8/87 9/87 10/87 11/87 12/87 1/88 2/88 3/88 4/98 5/88 6/88 Month Reported I
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BECHTEL WORK PACKAGE CLOSE-OUTS July 1987 - April 1988 80 - e.n e.73 N 70 -- o.m l
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i PILGRIM STATION NUORG OVERTIME ' 7000-- ' 6000-l 5000- , H 4000- ! O 3000- - E l
!= O Jan-h;ii;llmi i ;
Feb- Mar- Apr- May- Jun- Jul-88 Aug- Sep- Oct- Nov- Dec-IIilI; ; ; ; ;
- 88 88 88 88 88 88 88 88 88 88 88
! Note: Figures are a E FRCST G ACTUALS l weekly average i
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PILGRIM STATIOU A 7 ~J"~' NUORG STAFRNG . ' 24kf
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l YO_ -t5 [ 10 M 900 - A 800 - l Jan- Feb- Mar- Apr- May- Jun- Jul-88 Aug- S6P- Oct- N ov- Dec-88 88 88 88 88 88 88 88 88 88 88 E FRCST 8 ACTUALS l i
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i l NON-CONFORMANCE REPORTS (NCR'S) l 40-l l 33 30-I 20- ; 2/1 3/1
, Ohh 4/1 hhb, 5/1 6/1 OPEtJNCRs POWER BLOCK NCRs
- _ _ - . - - -- .- - -__ O
QUALITY ASSURANCE RECOMMENDATION TRENDS (FOR PNPS ORGANIZATIOt4 70' O 61 61 P 60 - - 50 46 N - 40- as O 3o f A 21 20 i9 20 7 R _ 14 - 13 12 10 ~ 7 - 10 _ 7 - s 3 0 0 O g .,;, 0 ' FEB 1,88 MAR 1,88 APR 1,88 MAY 1,88 JUN 1,88 i OAR MONTHLY STATUS mll: O ll & C ll 3 C T O
TOTAL OPEN MRs 3500-- ., als E s 3000-in Test & Turnover 2500- ,, .l ' i 2000-l 1 i 1500-1000-500-0'...: ,.,: : : : : ..: ,.: :': : :I: : : : ,.,: ..:.: ....,,.........,,.. ' 5/29 6/26 7/24 8/21 9/18 10/16 11/13 12/11 1/8 2/5 3/4 4/4 5/2 5/31 0 Total open uns B All Other Open 1988
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L . PLANT DECON lb4*N s 4, 85- - 5/29 6/26 7/24 8/21 9/18 10/16 11/13 12/11 1/8 2/ 3/4 4/4 5/2 5/31 l 1987 1988 i
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- e COMPENSATION FOR TRAINING I
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RESTART PLAN REVIEW RESPONSIBILITY I. Review plan for its adequacy to resolve restart concerns list, plus generic concerns as defined by diagnostic inspection and by Dr. Murley (DRP will provide reviewer instructions). II. Determine if additional information is needed from licensee. If so, develop request. III. Factor applicable public, local government and state government comments into NRC review. Develop written disposition of these outside comments. IV. Select items that should be verified by NRC. Either conduct the verift-cation inspection or, if appropriate, recommend to the Panel, items for inclusion in the Readiness Team Inspection. 9 I 4 i ) I i i RESTART RESPONSIBILITY - 0001.0.0 i 12/08/87 l l
.. .... ,: . . . . a . ~ /. :. . . . . . . . . . . ..
. INSTRUCTIONS TO REVIEWERS OF THE PILGRIM RESTART PLAN I. Review Instructions The purpose of NRC review of the plan are (1) to assess its adequacy to correct identified concerns, and (2) to assist in planning for NRC inspections.
Review your assigned portion of the pisn and determine its adequacy to address the applicable portions of the NRC Restart Panel Concerns List (Enclosure 1). Document any concerns that do not appear to be adequately - addressed -- include your justification. Identify items that are not sufficiently detailed or where more information is needed -- write down as a request for additional information (See Enclosure 2). List those items for which a verification inspection is recommended. Dis-cuss with your management whether the items should be verified by a specialist inspection from your division or should be forwarded to the Restart Panel for inclusion into the Readiness Team Inspection Plan. Finally, af ter reviewing completely your assigned section of the Plan, review the following lists:
-- Factors inhibiting progress, as defined by 1986 Diagnostic Inspection (See Enclosure 3).
-- Items specified by the Regional Administrator as general restart prerequisites (See Enclosure 4).
If after the above reviews, you have broad concerns regarding the adequacy of the Plan, provide those to your Restart Panel representative to discuss with the Panel. While reviewing the Plan, complete the Restart Plan review matrix for your assigned section (See Enclosure 5). II. Schedule:
-- Complete individual reviews January 8 Complete supervisory and management reviews and forward written results to Restart Panel January 18
-- Forward RAI, if applicable to licen te January 29 l
l RESTART RESPONSIBILITY - 0002.0.0 12/08/87 , i
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-r;. .. - 1 i ENCLOSURE 2 4 Sample Request Format For Restart Plan Information I. Review Area: (List Restart Plan Volume, Section, Title) II. Please describe how the Restart Plan addresses the following concerns: A. B. C. III. Please provide the following additional information to clarify or amplify stater.ents in the Restart Plan. RESTART RESPONSIBILITY - 0003.0.0 12/08/87}}