ML20205E294
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December 10, 1987 I
Docket No. 50-293 I
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LICENSEE:
Boston Edison Company FACILITY:
Pilgrim Nuclear Power Station
SUBJECT:
Meetina 9etween Boston Edison Company and NRC, on November ?4, 1987 t
On November 24, 1987, representatives of Boston Edisen Company (BEco) met.with i
i members of NRR and a mem5er of the public to t/iscuss fire protection ' issues
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r recarding the Pilgrim Nuclue Power Stetien. Significant matters dis:ussed are sumarized in Enclosure 1 to this memrandum. Enclosure 1 is formatted t.c i
l correspond with the meeting agenda issued November 13, 19R7 A co'py or the meetino I
agenda is attached as Enclosure ?.
Attendees are listed on Enclosure 3 to this i
memo.
I sincerely, r
l Uriginal signed)g i
Richard H. Wessman, Senior Project Manager Project Directorate I-3 i
Division of Reactor Projects I/I!
1 Enclosures As Stated 1'
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JOHNSON 00-190 PDR
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e Sumary of Fire Protection Meeting Retween Boston Edison Co. and NRC on Nnvenber P4, 19A7 With respect to Exemption Requests 11 and 12 (TAC NO. 53416) BECo presented a layout drawino of the minus 17 foot level of the reactor building L
with a revised inventory of combustible material in each of the fire zones of interest.
This formed the basis for discussions on the location / separation of redundant trains of safe shutdown equip 34nt.
The following list of combustible loading is based on what was found when the most recent inventory was taken and, in some cases, includes materials issociated with the ongoing shutdown which will be removed prior to restart.
9 Fire Zone Combustible loading 2
BTUs/FT 1.1 15,767 1.2 14,870 1.6 11,110 1.8 1, 58 3 i
1.30A 1,429 s
NRC agreed to detemine whether there should be some specific limit on the amount of combustibles in the zones associated with these exemtions.
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Subsequent to the meeting, the staff determined that, in the event of a I
transient loading exceeding that which constitutes the basis for this exegtion, the licensee would be expected to inform the NRC and institute appropriate
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cogensatory measures.
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!!. BEco provided the followine infarm tion on Exemption Request No. 21:
(1) The fuse boxes are access',ble and sufficient lighting l
1s provided e"en considering the effects of smoke.
(2) The spare fuse is locsted in the box and it is obvious where it goes.
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In addition the time to complete the task (15 minutes) vs the tine available before an unacceptable situation develops (2 hrs.) was discussed. These time estinates and the supporting informetion are l
contained in the original submittal.
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!!I. BEco provided the Appendix to this enclosure, which prwsents the status of j
i all Appendix R exemption requests. During the accompanying discussion it i
was determined that no reviewer retources are expected to be assigned to t
Exemption Requests 15, 18, 22 (TAC N0. 6599) for the next 40-60 days with completion of the SER estimated for April 1988. NM agreed to determine j
whether Exeg tions Requests 15, 1A and 22 should be completed prior to j
i restart of the Pilgrim Plant, and if so, to arrance fer the assionment of i
a higher priority to this task.
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!Y. The actions associated with Appendix R Technical Specification changes 1
(TAC No. 54610) were discussed. BEco state 6 that the letter with the t'
I required comitrwnts has been completed and is circulating for j
signature. Based on BEco's description of its contents, it appears that j
the submittal will be accaotable when received. The SER is essentially l
complete and is awaiting receipt of the SECo letter as a reference.
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Y and VI Inspection Report 50-293 87-39 identified potential deficiencias in the fire resistance of the control room floor and with the fire ratino/ sealing criteria for conduits.
The BEco engineering evaluation of the adequacy of the enntrol room floor will be submitted to the NRC for review since it bears on the basis for granting exeretion #18, The evaluation will point out 1
i that the cable spreading room and the control room above it should be i
t censidered as a single entity for fire evaluation. That is, a fire in either location requires that the plant be shut down using the alternate shutdown panel. Therefore, the fire resistance of the barrier between them is not of concern, 1
A new criteria document for conduit sealing, based on Cleveland Electric data which has already been accepted by NRC, should be co m leted by the end of December, An engineering evaluation which is based on that document will be provided by BEco in response to the inspection findings on i
conduit seals, j
VII. A general discussion of ongoing or anticipated fire protection issues l
l was held in order to help NRC plan for the essignment of reviewer 1
resources.
It was concluded that all issues were covered eitl,er in the status report (item !!!) or in tne inspection report responses (items V and V!), with the exceptions of some fire doors with minor imperfections in fit.
These will be the subject of a BEco engineering evaluation wnich will be submitted to NRC, g
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Boston Edison Company Apobndix R Exemption Reauest Status Number Description Submitted to NRC Status E3 #01 B CoreolRoom-Imm pmveng a fined 3/18/81 Letter 2 81.059 Grcsed - leser fem NRC 11/10,81 (1.81336) suppression system ER #05 Torus Waer Level-Ezenpeion from Submeted Sedion 35 BECo. Letter to Grarted by NRC 6/10/85 (1.85.191) PDC 85-41 (R@ndant)
P*"9 8"o desecsion and automatic NRC 6/25/82, ~BECo. Response to sapprorsionin me Torus Coppartment Appendix T ER #06 Torus ww Tenprasure Contured wth Torus WMer Level Grarted - Contaned weh Torus WMer Level Exempton Exemption Request submeted 5/17/33 Re(pest #5, PDC 85-41 (2.83.130)
ER #07 Roador Butent, Water Curtain (El Submetal Section 35, resubmeted Granted by NRC (1.84379,1.85.191). See PDC i
23' 0") Emengsen trom providmg an 3/11/83 (2.83.069), 5/17/83 85-049A and 0490 ausomaecfire suppressen system (2.83.130), info. 4/2/84 (2.84.049),
throughout fire zones 1.9 ed 1.10 (2.85.057), (2.86.009) and (2.86.084) l ER #08 Heador haareng Waeer Curtam(El SubmetW Section 35, resubmeted Gransed by NRC (1.84379,1.85.191). See PDC 51*-0") Esenpeion from provdng an 3/11/83 (2.83.069), 5/17/83 85-049A and 0498 aimomaecfue suppressen system (2.83.130), Info. 4/2/84 (2.84.049),
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throughout lire zones 1.11 and 1.12 (2.85.057), (2.86.009) and (2.86.084).
See Exemption Re< pest #7 i
ER #09 Areas wien anomane CJdown and re Submetd Susion 35, Resubmeted Gransed - See NRC letters (1.84.379 & 1.85.191) shed fire suppressen syssem 5/17,t3 (2.83.130) tmi of rased sire benter beeween Torus 11/1%1 R.83 281)
HRC lssued the Erw.u..retal assess r.wg and i rs.r.g Cooperimert and the CRD Oua'sant 7/28/86 (2E6.110) of no sagndcare irrpa::t approvmg the exempeers for ER #11 11/14/86 (2.86.176) pubicaten in Federal Register dated 9/16tB7 ER #12 tack of rased fire barrter between Torus 11/t6/83 (2.83 281)
NRC issued the Erwwonmortal assessment ard Ireng
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Conpartmert and the CRD Ouadrant 7/28/86 (2E6.1101 of re signdcars errpacs 4 proving the exempson for 1 /14/8E (2.86.176) pubicasen in Federal Register dated 9/16/87 i
I November 20, 1987 Page 1 y
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, Boston Edison Company Appendix R Exemption Recuest Status Number Description Submitted to NRC Status ER #13 unpme.csas Swucsural Saeet in the 11i16/83 (2.83 281)
NRC issued the Erwironmertal assessment and fedog Torus Conper1 ment 12*27/84 (2.84 214) of to sagnecart irrpact approving the exemphon for 7/28/86 (2.86.110) puticahon in Federal Register dated 9/16/87 11/14/86 (2.86.176)
ER #14 Unp'atecsed StrucsuralSloolin the 11/16/83 (2.83 281)
NRC issued the Erwwonmertal assessment and findng Steam Tunnel 12/27/84 (2.84 214) of no signihcars irrpact approving tra exemphon for 7/28/86 (2.86.110) pubhcahon in Federal Register dated 9/1667 11/14/86 (2.86.176)
ER #15 No 34tourIlse benter between Comdor 8/10/87 (2.87.135)
Grouped weh Exerrption Requests 18 & 22.
8137 (FZ 3.9 partial) out side the compuser som and she Radmaste Aron (FZ 3.7) at El(-)1*-0-(dI:G2.6)
ER #17 Emergency Ligtning Outsue of the 4/1/87 (2.87.053)
SER ksued by the NRC dated 10687 Budding i
ER #18 Have not povided a fue 20 feet of 8/10/87 (2.87.135)
Grooped weh Exernpton Requests 15 & 22. Submeted horizortal dearance wiIhold irderwening to NRC on 9/10/87 con maanNag, *A* train Cables lor Wie e
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Service Water Pumps, ROCCW Puny and she *A* Dessel Fuel Od Transfer pungs are Win the acid neuwaaring sun,whchis part of she WTR (B Fire Area 1.10) i ER #21 Fuse sut==nent as a repan and 10/2/87 (2.87.160) d gg kapenne lor #= quadrare cooter ER #22 Exongkon kom fue area delocson and 8/10/87 (2.87.135)
Grouped weh Exempton Requests 15 & 18.
l fixed sappressson in the Reactor j
Auxiliary buikkng to separate lotus water j
levellines.
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Page 2 November 20, 1987
e AGENDA FIRE PROTECTION MEETING 11/24/87 ROOM 116 10:00 AM TO 4:00 PM I.
Exemptions 11-15 (TAC N0. 53416) Clarify Location of Redundant Trains and Quantity of Combustible materials in each Fire Zone.
II. Exemption Request No. 21, Fuse Replacement as Repair (TAC N0. 66369).
III. Aprendix R Exemption Request Status (update of 6/26/87 Table).
IV. Fire Protection Technical Specifications (TAC NO. 54610) Clarify supplementa1 information to be provided by BEco.
V.
Control Room Floor.
VI Conduit soals fire rating.
V!! Other potential fire protection actions to be accomplished prior to restart, in conjunction therewith or shortly thereafter.
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Attendance List - Fire Protection Meeting 11/24/87 Room 116 i
E Name Croanizatinn t
Owen Gornley NRC PD I-3 L
Bruce Boger NRC David Notley NRB/ECEB 4
Joseph L. Jerz BEco Paul A. Rainey BEco Bob Grazio BEco William Sullivan BEco T. A. Verkataramon BEco R. L. Kirven BEco Stephanie Murphy J
Thyagaraja Chandrasekaran NRC i
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k PRIORITY ATTENTION REQL11 RED IRIRWING ReptRT e RECI0lt !
OCTORER 22. 1987 u esasee/rectitty s.a t ricet tes/setje:t Salen Welt 1 40/22 Rt Feu SW 304272 Fireenteh sleep Esset At apprestemtely 11:00 p.m. se 10/21. tue Inc asetth Phyelee inspectore idsetitled a firesetch en the 100 ft. elevation of costelement she appeared to be sleeples se top of a large ter$1 hoe. h firouetch see eastseed to reve the Watt I costelemmet emee per heer. N liceeeee's fireestch espervleer use mettfied. N fiteuetch see rettere t of his dettee med te vedermatog f atecas for dety teetteg. Beattne reefdent felleesp.
_. _Neeeeee/Factitty not 8 f test f ee/%bject Pflerte 10/23 Rf PC h
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se 50e293 Reector DetIdtag Area Centesteettee
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on 10/20 et 4:05 p.:n. morters se the 23 feet ele.ettee to the reacter hos tatest noted meter hechtag op free a veret f?ser dretes. The cegtrol rees had preetowely diepetched se ops >,d er to begia dretates seter free the area betweeve the opent feel poet getee. The Ifeeeeee believes that the drete Itse from the hj
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Feet peel gate sees med the fleer dress pretee ehere a ceummes discharge to the 6
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reector betidies fleer drete easy. Righ flee, elevottee head and Itse bietejpge
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gg any hee,resulted to the opt 11. A 1erge sees of the 23 feet elevettee f a the reacter buildtog meer the east and euet hydreotte coettet sette end the drywell
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accese more constentateted with lesele of three to ten hope /100 square ca.
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g eestrel reos eso mettfled by peroommet to the eroe med the desteleg wee g
h teamedletely etopped. aselth penyetes techstetene to the eres evecosted the 8
eteestfee med ettelmed air semples. We ettberse centesteetfew wet identtifed and the stee see ly decentesteetod. N reefdent tempectore are k
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MEETING BETWEEN BOSTON EDISON AND r
a NRC SENIOR MANAGEMENT I
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9/24/87 - 1 p.m. - 4 p.m.
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l Phillips Building - Conference Room P118 Bethesda, Maryland l
AGENDA t
i NRC Introduction Boston Edison Introdu'tinn Restart Plan l
4 Management Improvements l
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Closure of Destart Regulatory Responses Power Ascension Program and Management Assessment Process Outage Scope anc Schedule I
Safety Enhancement Program 1
Offsite Emergency Plan l
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Action Plan i
j Concluding Reinarks Boston Edison NRC i
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TECHNICAL ASSIGNMENT CONTROL I
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