ML20033D825
| ML20033D825 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/06/1984 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Liaw B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082410577 | List: |
| References | |
| FOIA-92-463 NUDOCS 8402130133 | |
| Download: ML20033D825 (1) | |
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February 6,1984 7
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i HEMORANDUM FOR:
B. D. Liaw, Chief Materials Engineering Branch, DE FROM:
A. Schwencer, Chief Licensing Branch No. 2 DL
SUBJECT:
RESPONSE TO ACRS CONCERN 5 Off IG5CC FOR LlHERICK i
The ACRS initial neeting on the lirerick operating license application was held in October 1983. A copy of the Comittee's related letter is attact -d.
f wherein the Comittee reccerended "that the applicant develop and maintain a careful surveillance program to identify any factors encountered during plant operation wnicn nave the poientiel Tv, s.6ts f&ls damages." While the l'
Comittee did not specifically indicate that it would return to this stbject in the future on tirerick, we feel it would be prudent to be prepared in the event that reed does arise.
i We have addressed this ger.eral subject in our tirerick SER and in the SSER.
The Philadelphia Electric Cocpany has recently addressed the ACRS's staterent
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in their letter dated Jaruary 18, 1984, which has been distributed to you by 9
klDs. A copy is also attached to this ne w andum. Please review the applicant's response and provide re with your SSER input by February 15, 1984.
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1 A. Schwencer, Chief I
Licensing Branch No. 2. OL i
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DISTRIBUTION:
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UNITED STATES NUCLE AR REGULATORY COMMISSIC,N
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,, f ADVISORY COW.tl1 TEE ON REACTOR SAFEGUARDS i fc.y
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nuemet o=.o c. rem s,, v p October 18, 1983
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l; Honnrable flunzio J. Palladino Chairman U. 5. Nuclea-Regulatory Contsission Washington, 0 20555
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SUBJECT:
ACRS INTER!'4 REPORT RELA 1ED '.0 TrtE OPERAflNG LICENSE APPLICA110N FOR THE LIMEr.!CC GENERA 11*lG STAi!ON, UN!!S 1 AND 2 During its 282nd meeting, October 13-15, 1983, the Advisory Committee on Rea: tor Safeguards reviewed the application of the Philadelphia Clectric Company ( Applicant) for a license to operate the Limerick Generating Station, Units 1 and 2.
There was a tour of the facility by members of
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the Subcomittee on the morning of October 7,19t3.
A Subcomittee setting was held b Pottstown, Pennsylvania on October 7 and 8.1983 to consider this application.
During its review the Cormittee had the benefit of discussions with represtatstiiEs of the Applicant and the MRC Staf f and an oral presentation by a neeber of the public before the Subctnaittee.
The Ccmittee also had the benefit of the docusents referenced.
The Cos-mittee comented on the application for a permit to construct this Station in a report dated August 10, 1971.
i The timerick factitty is ioce:ed near the knuylkill River about 1.7 riles j
sout neast of the limits of tre borough of Pottstown, Tennsylvania.
The l
s:te is about 21 c11es nortn-est of the nearest boundary of Philadelphia.
Ine timerict Generating Station uses BvR 4 eoiling water reactors suppitec by the General Electric Ccnpany.
Tne pressure suppression contairnent system uses the General Electric Mart !! design.
The power rating of each untt i s 3 ?93 Ma't.
Bechtel Power Corporation is providing architectural, engineering, construction, and startup services.
Construction on Unit 1 15 about 90 percent ccriplete,. nd construction on Unit 2 15 aoout 30 percent c ompl et e.
The nuclear steam supply system and the containment system are almo;-
icentical to those of the Suscuchanna Steam Electric Station which was revie ed for an operating license with an ACR5 report. issued on August 11, 1991 i
Because of the uncertain schedule for U. wit 2, the Comittee does not b'elieve j
tt appropriate to report on Unit 2 at *. bis time.
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included an evaluation of the rianagement or9antration, the s
Our review operational staff, and the training progre for the operating and mainte.
nante stof f.
The tour ef the f acility by ACE 5 members included the power i
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Honorable hanzio J. Palladino October 18, 1983 pl ant simulaivr and the teaching laboratories housed in the training center which is located near the Limerict site and used extensively in the training e
of plant personnel.
The Linerict Generating Station is the Applicant's second nuclear station.
The Applicant operated Peach BottCA, Unit 1 a gas-cooled reactor, frcn 1967 l
i.u 19M o.4 7.a > @ e.~6t u p u c.. C ttom. 'Jr.!!s ? and 3, which are boiling water reactors, since 1974 During our discussions, the Applicant demon-strated an estensive kno ledge of the operation, design, and construction features of the pl ant.
We conclude that the Applicant has the necessary technical and management Capability to operate the limerick Generating Station.
Stress-assisted corrosion cracting of prieary system ccnponents has been observed in a ntnber of operating General Electric nuclear steva supply sys.
tens.
The matertals being proposed for similar ccnponents in the Limerick Station are believec to be much improved. We reconcend, however, in view of past esperiences, that the Applicant develop and maintain a careful surveil-i i
lance program to icentify any f actors encountered during pl ant operation which have the potential for materials damage.
The NRC 5taf f has not ccnplet ed its review of the energency planning for the Linerick Generating St ation.
We expect to review this subject in later meet t np =tti the KRC Staf f and the Appilcant.
he also plan to review the secu ity plen for the L1,ertet Station.
r in res:ense to a recsest from the MRC Staff, the Appilcant sutoitted a proba-bilistic rtst a sse ssme nt (FRA) in March 1981.
A supplement to this report i
wa s sv>ttted in Apr t) 1983 in the form of a severe accident rist assessment (SARA) report.
In its meetings with the Applicant, the tcmittee reviewed a nunter of plant f eatures that had been identified during the PRA and have Deen codifte in order to reduce risk produced by certain hypothesized acticents.
Tne f.RC Staff Safety 0 '"ation Report for the Limerick Stat.on cors not e.ite cirect use of the infore.;. tion contained in the PRA and in SARA b st rever folle-s tne guidelines of the Standard Review Pl a n.
The manner in -nics tne VC 5taff will use the PRA and SARA 15 described in NRC 5t a f f letters to tne Atomic saf ety and Licensing Board dated April 13 and May 24, 1983.
In inese docunents the NRC Staf f states that the PRA and SARA will be used to ccrpare the risk presented by the Limerick Station with that frcn ott,er n:,: lear po er pl ant facilities.
If thi, risk is found to be sign;f t-7 cantly greater than trat associated with other suc h f acilities, the NRC Staff.31) constear tne need to recommend compensacory features.
The NRC Staff's review of the PRA and 5 AR A 4 5 continuing.
We espect to review the PPA and SARA with respect to t he methodelogy, results, and use in the L ir.e r i c h licensing process.
We believe that the demography of the site s
c alls f or e c a re f ul consiceration of th results of the PRA and the SLRA.
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i N norable Nunzio J. Palladino October 18, 1983 The Co rnittee has, in several prior operating license reviews, noted the
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importance of assuring that the selsnic contribution to rist is accept-e ably low, with allowance for lower frequency, more severe sets:nic events than that considered as the safe shutdown earthquate.
This issue is ad-dressed in the SARA report. We intend to explore it further in our continu-l ing review.
We wish to consscer rurtner HEC Steii vie.s concerning the failure modes anc consequences of the main cooling towers during severe natural phentnena explosions of materials transported by rail.
Our concern is with the or j
close proximity of emergency and residual heat removal service water pipine and pcwer supply conduits to the cooling tower basin.
We have not co:pleted our review of the timerict Generating Station.
We co conclude that Unit 1 is well constructed and well managed.
As indicated above, matters still to be reviewed are:
emergency planning, plant secur-l tty, cargins against less probable tut more severe seistnic events than that considered as the safe shutdown earthquate, consequences of cooling tower j
l failure, enri the PRA and SARA.
We will report on these catters in a subst-letter.
However, at this stage of our review, we believe that fuel quent loading and reactor operation at 5 percent power can be carried out without undue risk to the health and safety of the public.
j J. J. Ray dic not participate in the Co-rtittee's considerations regard-l Kr.
in; inis matter.
i Sincerely.
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Jesse C. Ebersole Acting Chat ruan 1
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References:
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^ntiaceiphia Ele:tric Company " Final Safety Analysis Feport, Limerick 1
Generattnp Station, Units 1 and 2,* Volutes 1-16, and Atendments 1-21 I
" Safety Evaluation Report Related to the Operation of Limerick Generating
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St ation, Units 1 and 2,* USNRC Report WR[G.0991, dated August,1983 4
Fr tladelphia Electric Company, *Probabilistic Rtst Assessment, Limerick
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3.
Geoerating Station,' Voltrnes I and 2, dated April,1982 and PRA Proprie-tery Yelmes *5ystee tevel Fault Trees,* cated A,prt),1982 and *0uantifi-l Event 1rce Funtttons," dated June, 1982 cation of Limerick Keport prepared by NUS for Philadelphia [lectric Ccapany *5evere Acci-l dent Risk Assessment, timertck Generettng Station," Voices 1-11, dated Or 11,1983 i
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P O. 00X 8699 1881 1981 PHILADELPHI A. PA.19101 JAN 18 $84 msie4.asos
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Mr. A. Schwencer, Chief Dceket Nos.: 50-352 50-353 Licensing Branch No. 2 01 vision or I.acensing U. S. Nuclear Regulatory Coacnission washir"; ton, D.C. 20555 s
St.bj ect :
Lirierick Cenerating Station, Units 1 and 2 ACRS Letter Dated Octcher 18, 1983
References:
(1) Letter frota A. Schwence r to E. G. Bauer, Jr.,
dated November 14, 1983 (2) Telecon between R. E. Martin (NRC) and P. A. Tutton and J. L. Phillabaum (PECO) on December 2,1983.
I file:
GCNT 1-1 (NBC)
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Dear Mr. Schwencer:
The reference letter requested Philadelphia Electric to respond to ACRS coene nts on stress assisted corrosion cracking of primary systes eceponents and the potential main cooling tower failure modes and censequences.
Enclosed are attact.ments providing additional information to address these ACRS ccecents as agreed upon in the reference telecen.
Sincerely.
Id[
JTP/gra/011784305 d
t.nclosures 4
Copy to: See Attached Service List e#
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04012402 O IB PDR A ".
OS 52 PM A
l a:: Jui;e lawrence Brenmr (w/ enclosure)
.Ange Peter A..%3rris (w/ enclosure)
.Adge Richm1 F. Cble tw/enclomire)
Troy B. Conner, Jr., Esq.
(w/enclostre)
Ann P. Ibdybn, EM.
(w/ enclosure)
Mr. Frank R. R2run (w/ enclosure)
Mr. Rotert L. Antfony (w/erclosure)
Mr. Kuvin I. Lewis (w/erclosure)
Ms. Phyllis titzer (w/ enclosure)
Charles W. Elliott, EH.
(w/ enclosure)
"Jori G. Ferkin, Esq.
(w/ enclosure)
Mr. noms Gerusky (w/ enclosure)
Director, Pennsylvaria DxrgeIcy.tragcTnt Itjency (w/ enclosure)
Mr. Steven P. Hershey (w/ enclosure)
Angus Icee, Esq.
(w/ enclosure)
.ur. Joc~#. H. Sim. III (w/ enclosure)
David Wersan, Esq.
(w/enclostre)
Robert J. Str,ar:mn, Esq.
(w/crclosure)
Mutin W. Eush, Esq.
(w/ enclosure)
Sperce W. Perry, Esq.
(w/ enclosure)
Jay F. Cutierrez, Esq.
(w/crclosure)
Attru e Safety ard Licensirn 7qposl Baard (w/erriosure)
Atmic Safety ard Licensiin Board P.'uel (w/erclosure)
Etcket ard Service Section (w/erclosure)
James Wiggins (w/crclosure) e i
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AiiAChMENT I l
desponse to ACRS Concern on ICSCC F rom TS. t r let t e r of 10/18/83 l
The primary pressure Sounda ry a t Lime ric k is coeprised of both carbon and stainless steels.
ICSCC is not e spec t ed in carbon steel.
l The present condit ion of the timerick stainless steel pipe-ts described.
l tn nur letter to t he Coemis s ton, J. S. Keeper t o D. C. Eisenhut, da t ed
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10/5/83. This letter de sc ribes the extensive improvements which have of the been made to mitigste ICSCC including the complete replacement l
recireclation systes piping and the replacement of major portions of 7
other stainless steel systems with ICSCC resistant material.
In addition.
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l all of the class I. !! and !!! piping vill be subjected to' inservice l
inspection in accordance with ASME Section XI as augmented by h*UREC-t 0313. Revision 1.
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The operating staf f at timerick has reviewed all of Ceneral Electric's S e rvic e Inf orma t ion Le t t e r. (Sits) and the Nuclear Regulatory Commission's l
1.E. Bulletins. I.E. Kotices and I.E. Circulars which address IGSCC and have incorporated their recocnendations as appropriate.
In_ addition I
primary coolant chemistry ts regulan.y =vulivsed to maintain conductivity i
and chlorides within Technical Specification Limits. These !!mits are intended to sitigate ICSCC. Limerick has also added advanced analytical capabilities in order to monitor trace impurities which are believed to have an effect on stress corrosion cracking. We _are currently evaluating a program wherein by monitoring these impurities and changing plant oreratton as.ppavy..:.. :he ;rctat!!!:7 ef : tress corrosion cracking i
ceuld be further reduced.
L rhiladelphia Electric is also monttoring the experimental activities
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l of EPRI. CE and others concerning the ef f ects of veter chemistry on i
pressure bounda ry satorials. Particular interest is being given to the The
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s tudy of hydrogen injection as a means of sitigatics cracking.
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results cf these studies will he revteved for applicability to Limerick a nd incorporated as appropriate, i
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