ML19206A323
| ML19206A323 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/10/1978 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19206A317 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7904190312 | |
| Download: ML19206A323 (4) | |
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UNITCO OTATES
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5 NUCLE AR REGUL ATOR Y COM'.MCICrJ
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Introductica 1.
By letter dated February 17,1978, etrcpolitan Edison Ccacany requested amendment of Appendix A ~'ec".nical Specificaticns of.ne license to fulfill t.".e r e_.a k. u......
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.u allowable voltage and fres.:cncy variaticns for a 500 xilcwatt lead rejection trcm t.e emergency clesel generators.
2.
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3.
By letter dated February 23, 1973, Metrecolitan Edison stated that their prior letter of Fecruary 17, 1978 documented cegliance witn t.e folicwi.g paragraphs of the license:
a.
Paragraph 2.C. (3).l.1, rec.uirino revision of desic.a details of c
an automatic water suppressica system in e;ch diesel generator room basement.
b.
Paragraph 2.C. (3).l.2, reouirinc. c. rovision of a fire.,ater cite n
rupture analysis and design of water cpray protectica where.
required.
Discuscion 1.
Para 9rach 2.C. (3).b of the licence rec.uires Metrco.olitan Ediscn Cc.m. a c/
to submit c. rcc..csed allcwable voltac.a and frec.uency variaticns for a 500 kilowatt load reNctica from the emercency diecel ceneratcr3 fcr incl;-
.c.. '-. 4.#.; c a ~",,*. 8.1.1..'. u. 3, e. " - *o ir.4 4 1 s io n in '_'...7.' - ' 1 v.
into Mode 4.
Metrocclit.;n Edicca Co rany nad been una. ale tc ascerta ta all the required information prict to iccucnce of the license and Technical ::xcir cations, anc we concluced at tr.e time tnat eccer.ce Of this Cur'.*eillrr.ca require ~ent Jrior to entr*/ into rde 4 cw n00 reprc3ent a :isA C3 One health anC cafety of the pu;IlC.
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2.
We noted tv.o.oc>rac.hical and editorial errors en ca.es 3/4 3-7, 3/4 3-17, and 3/4 8-5 of Accendix A Technical Specificaticas.
3.
As a result of our fire protection review, we had recuired Metrecclitin Edison Company to cccplete various modifications and provide certain additional information to improve tne capability of the fire protectica system. Amcng these items were the following:
Provide design details for an automatic water suppression system in a.
each diesel generator room baccment. (License paragrach 2.C.(3).l.l.)
The licensee prcvided with their letter of February 17, 1973,
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.e Ecce Stations and Wet Pipe Sprinkler S"st..s".
The " wet pipe sprinf.er 1
systems" are the autcmatic water suppressicr. systems recuired. The sc.ecificatica describes the systems and cccr.cr.ents to be furnisned, inc.l ud. i..,...i.n.i...".. d a..a-i v -.". n. ' c, e o #. 0. 3 v^~c.1.#^ r "..'
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s area, seicnic Categcrv. I desic.n rec.uirements, and all applicaole Codes and standards.
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l i-e... e c_ o_ e r-oc _c a_ " * " '
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es prior to startup fclicwing the first regularly scneduled ref"el ing o, ~, *. c n.
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tmnt entation o dr.is propasal.
e b.
Provide the results of a firewater c. ice ruc_ ture analv. sis and desic.r qv,
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.e both divisicas of red;ndant safe shutdown eculpment could be incipaci-tata_d bv,.i..t'n *-.i c r.,1 o r u'c.i do_. i._'.' m' e r.1 '. '..i.n o #
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e paragraph 2.C.(3).l.2.)
The licensee provided with their letter of February 17, 1973 the res_its of their anal' isis. The diesel c.enerators are the cniv safetv.-related competents currently protected by a sprinkler system.. The diesel generator basements will be so protected, in accordance with 3.a.
.nc,_
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C's'_..' *- ;.7 o f
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e" a
c-achievement of cafe shutdcwn.
The analysis of rupture of the fire service piping indicates that all s"c5 ^g ie.i.c, i -
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o ae that because of the system rescura and tecperature, pip 2 wnip L
need nct be censidered. A tnrcugn-aall crack anywhere in the h
s',}
. system has been pcctulated, and the 1icensee determined that the leakage strean from this break will not affect both di/icienc of redundant safe shutdown ecuipment. Therefore, no additional water spray protection is required to p:otect against pipe rupture.
The licensee notes that water spray protection mc sures that may have to be taken to crotect redund.nt disicions of safe chutdown equimrent due to the application of manual firewater can only t
be determined af ter corpletion of the fire hazards re-analysis which will determine what equip.want is required for safe snutdcwn in the event of a fire in varicus areas. That analvs:s is scneculed to be cc o. leted by May 1,1973, and they exp2ct to be acle to prcoose an"2 hose spray protection measures required at that time.
Paragraph 2.C. (3).l.3 ac modified herein will assure that this is cone.
Evaluation 1.
We have reviewed the licensee's.crocosed allowable /ariations in voltac.e
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Specification 4.3.1.1.2.c.3, p. 3/4 S-3, as shown in tr.e attacn-an.
to this licence amend.ent.
2.
We have noted t".e following tv..cc.rachical and editorial errors in the Technical Specificaticas of Appendix A of the licen:2.
- c. 3/4 3-7.
In the Unit identification at the bottom of tne.cac.e,
_tne racility had been errcneously identified as Unit 3, rather than Unit 2.
- p. 3/4 3-E. Table 3.3-4.
In Sectica 7.b.2., Emergency bus ?2-lE chculd nave properly been identified as 42-3E.
- o. 3/4 8-5.
Section C.13 referred to an engire mounted fuel t:nk on eaca alecel. This f acility d es not ?. ave encine Taunted tan <a as dc
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m 4.8.1.1.3, tne numccc of diesel generator f ailures rey:nd snich supplemontal rcperts are required was errcnecu >lf identdi.,j as 4 7.
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Fosition reierenced Ec C. '. b, wnica should b2 C.3.o.
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- EValuatica For prccervice hydrostatic _e; ting and testing during the fir;t few Yearc of life, the reactor vessel closure head and outlet no :le control the prescure temccrature limits involvad in satisfying the fracture touannecs requirements of 10 CFR Part 50, Ac.cendix G.
Assuming ac.c. rc riate reference e
flaws and safety factors, Babccck & Wilce>. performe,i an analysis in accordance with the methcds of BAW-lC046A, "Med^ds of Corpliance with Fractura Toughness and Cperational Requirements of 10 CFR Patt 50, Appendix G" wnich shows that the minimum Tetal temoerature required for 2300 psi is ISO degrees Fahrenheit if no significant thermal stresses are present.
The licence 3 has confirred that the temperature will be essentially static (i.e., a very low heatup rate vill be emoloyed) which will minimize tner.ml stresses.
- ".e temperature will be meacured on the outside of de vessel closure head at its juncture with the flange, which is the area of hignest strecs.
We have rc. viewed the information provided cy the licensee and find it acceptable and in conformance with 10 CFR Part 50, Appendix G.
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-a for these tests without de presence of fuel are uncnanged.
t Based on the abovei we ccncluce that performance of hydrostatic testins 1^a e p r.i o r ' o.i.n. i"..; a 1' ~ 4.. i ca.l.i '.",.a.. asoc.v i n ' ' " -.." l e " = ~..e _. a *. ".- '_ o"
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u Techr.ical 5,recification 3.4.9.1 to permit such testing.
Enviro mental C nsideration We have determined dat de amendment does not audorize a change in ef flucnt types or total 2: cunts nor an increase in pcwer level and will not result S.av i r.3 4
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we have furder concluded that the a endrent involves an action wnich is insignificant frca the standcoint of envircn.: ental inact and, pursuant to 10 CFR $51.5(d)(4), that an enviccnmental impact staterant or negatile
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e connection with de iscuance of Sis amendmut.
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_ Conc..lun i on We have concluded, based on the conciderations diccussed avave, that:
(1) because the a:r.cndm:nt does not in;cive a significant inercase in the probability or consecuences of accidents previousi,, considerad or a signit icant decrease in any safety margin, it does not involve a significant hazards conside ration, (2) there is reaccnable accurance that tne healtn and cafety of the public will not be endangered F,
-e-n ation in the prey.. ;,nner,
and (3) sucn activities will bn anducted in ccmpliance with tne C0mmism.^n 's regulation: and the iss".co of this a cnitent will not be ini.nical to the common defense an security or to the health and safety of the public.
d Also, we reartirm our conclusions as otherwise stated in our Safety Evaluation Repcrt.
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Harley,S'il.ver, er0]ect ?.anager Light!'.;ater Reactors Branch 4
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The above errata are entirely tyccgraphical and editorial in nature, and have no negative ef fect on cafety hazardc ConsiCerations, safety margins, or t".e health and safetf of the publiC. We tnemfore Conclude that Accendix A, Technical SpecifiCatiCns Can and snculd te revised as indicated.
3.
a.
We have revieWCd the informatiCn provided by the licensea en the a vy. - n.c
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s o find that the systems as 3 eCified Can be exc.eCted to twform as rec.uired to crotect Caoles anc. equrment in tu.e ciese.,. generator a
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to protect against ne acclicatica of manual firewater, we concur that this can ce determined only after cogletion of the fire hazarcs re-analysis to determine wnat equiu ent is rc.pired for sc.Q snutccwn.
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environ. ental igact appraisal need not be repared in connection witn the e
issuance of tais ar.endment.
Conclusion b.'s. h m'". o.
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- i... activities will be conducted in e :mliance with the Ccmissicn's regulations and the issuance of this amen &ent will not be inimical to the cc. en cefense T
and cecurity or to the nealth and safety of the public. Also, we reaffirm our conclusions as otherwise stated in our Safety Evaluation Report.
./'
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//
Haric,,,5ilver, Projn
- V mager Light'/laterReacrorsBranca4 n
s d.f ).s vu[c.
U ll
[
iteven A. Varga, Chief T
Light.iater Reacters Branch 4 Division of Project tir.agemenc March 10, 1978 is*I A 4 (24mA e