ML19220B856
| ML19220B856 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/21/1978 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19220B857 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7904270471 | |
| Download: ML19220B856 (25) | |
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talve Aeac;a tests arya ot;.er va29e ar.c ;ca; tests required ;y tne Aai Ccde z.nculd ce revie.ic: far e_;a g
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Housten Lignting & Power Ccmpany APR 21 h09 CCSt cir. P. A. Horn Project Manager, AC.K;3 Houston Ligliting & Power Car.pany P. v. Box 17v0 Houston, Texas 77001 R. Gordon Goocn, Esq.
Baxer & dotts 1701 Pennsylvania Avenue, N. w.
.iashington, D. C.
2uuu6 Mr. Jonn Carham The hcuston Cnrenicle sul Texas Avenue ricuston, Texas 77002 ilelbert Scnwarz, Jr. Esq.
Baker & Botts 1 Snell Plaza Houstcr. Texas 77002 Kathleen Shea, Esq.
Lowenstein,iiewman, Reis & Axelrad lu25 Connecticut Avenue, N. L.
Wasnington, D. C.
2ud36 RCcert Fendergraft, Esq.
Office of tne Attorney General Environmental Law Section P. v. Box 12548 Capitol Station Austin, Texas 70711 I
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ErC ST AFF GUIDANCE FOP CC"JLYING SliH CE TAIM PROv!510uS 0 10 CFR 50.55at:1 "INSE;V!CE In5PECTICn RE0uttEnENTSE t
I.
.lNTRODUCTIO, 12, 1976 Paragrarn 52.55a( g) cf 10 CFR Part 50 was revised on February Since then, a nunder of licensees have recuested that
~{
(41 FR 6255).
clarify several key previsions contained in the revised regulaticn.
(1) the recuirenents to periodically the NP.:
These key Orcvisiens reitte to:
{
update the inservice and testin; progra9s to comsly~witn later editions and addenta to the A5'tE Code, (2) the requirement to conform the Technical Specificatiers te a revised. inservice inspection or testing program, and (3) tne er:cedures for requesting and c taining relief frcm AS4E Code recuire-ents tnat the licensee censiders to be in:cactical for Tne cur;ose of this docu-ent is 10 briefly summari:e I
hi s f acili ty.
550. 55 a( g) anc to prov. ice general the maj:r pr:/isions of the revised The document is in no way intenced l
guidance in these three key areas.
' to encem;3ss all aspects of attaining com;liance wi*h 150.55a(g).
II.
SWW:V 0F EEGULtT10H
[
contains previsions that recuire inservice ins:ec i The revi sed 150.55a( g) tion and testing of AStE Coce Class 1, 2, and 3 nuclear power plant ecm-punents (including su:: Orts) to be performed in accorcance with Sectio
(""""
For of the 15 :E E0iler & Pressure Yessel Coce and apolicable Adcend3.
operating f acilities whose 0:erating License (OL) was issued before March 1,1975, these previsions of the regulation a;oly at the start of t l The j
regular 40-month ins;ection period af ter Septem:er 1,1975.
ner.:
start of the rext 40-month period is determined by measuri'; a series of ;
F:
such peri:1s beginning at the start of f acility c:c9ercial c of the regulation apply at tne start of ccmmercial operation.
l, a
150.55ai g) new specifies As a result of the February 1975 amendment, inservice ins ection and testing requirements for all c;erating plants, including these that received a Construction Permit (CP) before January 1 Since plant designs and access provisions for inservice ins ectioni 1971.
j have pecgressed ever the years, the regulation provices rec:gnition of
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this f act by ge v;inc cesign requirements for component inspectability The regulation further specifie:
based on a f acility's CP issuance cate.
that new inservice inspection and testing requirements that bcccce effec-editions and addenda to the ASME Code, shall apply to all i
tive in later plants to the degree practical thecughout their service lives.
i q
6 p
11 u
v s.-
s.
8
..'. I
-g.
is the ih:orporation of the An important part of the revised 150.55a(g)
AT4E Coce Se: tier XI recuirenents fer testing pum:s and valves for cperr-This tne inser< ice irispe:tien recuirenents.
tional readiness sleng withto a f::ility's inser. ice insa: tion pregram, a ee ns tnat in acdttien of selected pg=ps.ar.d valves cust also De (A5;(tVttd periodic testin; progra9 for centinued updating of requirements There are new previsier.s in 150.55a(g)
The inservice for testing penps and valves anc for inservice inspec testin; pregrc" must be u::atec every 20 conths.
specifies a: tion to be taAen by c licensee when an updatec inservice tien er testirg : ngram conflicts with the Te:hnical Specifcations, or whe referenced ASME Cece Fdition or Acdence, is ia t a requirerent containedne.icensee cue to design, ge::etry, or caterial deemed ie:ca:tical by o consideratiens.
allow the NRC to grant relief fr;a ASME Other previsions in ! 50.55a( g) Code re uire e-ts that have teen c re:uire a licensee to foll:w an augmented and s:e:ifi: ally all:..he NRC t:
inservice insce:tien program on components for wnich accec assuran:e o structural reliatility is neecec.
5 elected previsions of the revised regulation are dis:ussed belcw.
~'
P for Cenpliloce with Three Key Provisions of 50.55a(g):
311.
General Guican:s P rocraes Urd sti"; 1.se vice instect; o' and Testir.:
A.
---r a re c re:n :..:: a t :; t 1 The inservice inspection ort; ram for a fa:0ity nust be updated at 40 month intervals, wnile the
-ogram fer testing pum:s and valves for A description c erational readiness must ce updated every 20 months.
of the updited programs sneuld ce submitted to the NR~ for review and approval as f ar in advance as possible of, but at least 90 days be The inf rmation tne NRC will need for its the start of ea:h p?riod.
review of updatec prograns is identifiec in Appencix A (attachec).
Under 150.55(g)(a), the revised inservice inspection and testin to the extent practical, c ply with tne recuirements programs.ust,in editions and addenda to the A5ME Cece that are "in ef f m
than 6 montas before the start of tne period for which the upcated The terns "in ef fect" or "ef fective", a s usec program is atelicable.in 550.55a(:)(a), identify tnese editiens and that have betn publisned by the ASME and tnat are also referenced paragra:h (5) of 150.55a.
e 9
83
p 1 P aragraph (b) c' 550.553 is amended periodically t0 incorporate more re:ent H: ever, the regulations are not amenced ASME Cece E5it::ns and A0denca.lished ASME Code Editions and Ad until af ter tre pub Therefore, the ASME Code Edition and Addenca tha:
by the NRC.
a y ins;ection period are tn0se referen:ec in paragrapn (d' and endorse:
See appli:able ::
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cf 150.55a er e cate that corres;:nca to 6 montns before sne pyrp pf the period in questien.
-i paragraph (b) of 150.55a bec:me effective en a'date"tha t f alls bet-sen t*e cate that marks 6 months before the start of' a. ins'pe:tien I f amend ents t:
period and the start date itsel f, the licensee is not required to comply Under the.regu-with the nes.ly eferen:ed A5ME Coce Editions and Addenca.
the li:ensee need only c:eply with the A5ftE Ccce Editions and Adcenca that were referenced in paragraph (b) of 550.55a e months before
- lation, the start of the CeriCd in Cuestion.
On the c;ner hand, the regulation d es not pre:Tude compliance with the later referenced editions and accenda
- that ces:ribes ea:n new inservice if the li:ensee chocses, but the docu-en inspe:tian er testing program sh:vic state wnich A5ME Cccc Edition and Addea s
will be uset.
An inservice ws;ection or testing program does not comply with f 50f 5 if it is based on an A5ME Code Edi:icn or Accendum wnien is not or has n i
p.=
been referenced in paragraph (b) of 150.55a.
Conf erkir; the Technical Scecifications to an Uodatec inservice Ins:ection i
8.
f ro:ca: ----
P a racra:n iv.55 ac c il:! t i t i:
cr lestin:
If a revised (= dated) inservice instection or testing program
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wi th the Techni:a1 the Technical Sce:ifications to conf:rm then to the updated pro-l changes This mus t be done at least 6 months before the sta-t of. the perioc g r a?..
in which the pecgra9 bec:ces applicable.
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f Technical 5:ecifi:ations are considered to be "in c:nflict" only in cases I
where the requirements of the regulation (thus the re;uirements ef the updated pregra~) are more restrictive than the recuirements of.the Tech-
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nical Specifications.7 such cases the licensee must propose changes to In cases wher.
conform the Technical Scecifications to the revised pr0 gram.
the updated crega, is less restrictive than a particular Technical Specifi-!
cation recuire,ent, the itcensee cust centinue to ccmcly with the Te:hnical Specifications until he recuests and is i: sued a Technical Specificati:n f
4 s taf f.will review such a pecscsed tecnnical 5:eci'ficati:n change. The N i
i change to detemine if it is accentable or wnether the existingge3 re-i ment sh001d be retained as an avgmented TMNement pursuant.to,p. o.
3 50. 55 a ( gl (6 )( i i).
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In the H2C Sta'f's view, the most e f ficient way to eliminate existing or potential r' iiirts frem the Tecnnical Specifications is for licensees to propose TE ' ic al Snecification cna,ges that woule suost'tute stancarc language rstarencin; 50.55e(g) in tne ple:e of existinc inservice inspection anc testing requirr,ent3.
This should be done at least
.6 months before the start of the first 40-month ins;ection period
.for which 50.55a(g) is a;pliccble.
Sample language for gni; purpose
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was sent to licensees ea*1ier this year.
The IRC strongly reto, mends that licensees adopt the approach of referen:-
ing 50.55a( g). because su:.5 referen:ing will sinclify the Technical Specifications by celetinc iny recuirements that are duplicated in the regul a tion.
It will also alleviate the need for enances whenever an inservice ins:e: tion cr testing prograc is uccated.
This approach has the added advantage of eliminating the sched Jiing pressures associated with meeting tre 6 renths submittal tice raquirement for Technical Spe:-
ification changes proeosal s of 50. 55a( g)(2 )(ii).
It will also simplify I
the process by w9ich licensees re uest, and the URO grants, relief from AS:'.E Cote recuirenents tnat have been determine: to be inprac*ical.
This is be:cuse license amencments (i.e., Technical Specification changes) will net be necessary to grant relief.
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Relief fr:m A5"E Code recuirements that are deemed impractical for a facilit -
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is further di s:Ussed below.
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r lief f re-c5n Cnde R ecuirements Determined to be Imnractical --.
C.
Obtainier e
P :ra:-a:- 50.5 t e '. e li 51( 111 ) anc to )(1):
If certain a5'1E Code requirements are found to be inpra:tical by the license the regulatien recuires him to notify the HRC and su:mit information to su::-
his find:n;s.
The licensee should submi~t requests for relief fr:0 AS1E Coce requirere9ts that he has cetermined to be in;ractical at least 30. days bef r the start cf the apolicable inspection perio0.
The information that is neet by the U C Staf f to evaluate requests for relief frem requirements found to.
inpractical is identified in Appencix 5 (attached).
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The HD.C Staf f will evaluate licensee requests for relief and will grant reli if appropriate, pursuant to 50.55a(g)(6)(i). Unless a licensee is etnerwisc '
notified by the lac, relief from ASME Code requirements will remain a:;1icab.
until the end of each 120-month period.
At that time, the HRC will re-evalc,'
the casi s for the determination that the re;uirement is im:ractical, pursuar' to 60.55afg)(5)(iv).
This re-evaluation will take into account any acvance in the sta'.e-:f-the-art.cf inservice inspection techniques tnat may have occurred since the relief was originally granted.
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Generally, the licensee will know well in advance of tne beginning of any inspection ;eriod, whether or not a ;3rticular ASME Coce requirement will be impractical fer his facility.
Thus, the licensee should request reljef
'from A91E Cece re:uirenents as f ar as possible in advance of, but 400 less than 90 cays before, tne start of the inspection period, Earty submittals are particularly important for the first 40-month inservice inspe: tion and 20-m: nth punp and valve testing perioc because they will enable the N?C staff t: evaluate the information received froc3all licensees and determine which A9iE Code recuirements may be generally impractical for various classes of plants.
Early submittal s will 'thereby f acilitate earlier feedback to licensees regarcing the a::eptability of their requests.
The li;.C Staff rece:ni:es that it will not be possible in all ' cases for.a licensee to dete rrine in acvance tnat any particular ASME Code re;uire-ment will be im;ractical for his facility.
In cases wnere, during the?
process of ins:e: tion cf testing, certain re:uirements are founc to be unferseen circumstances, ti e licensee may request relief impractical due t:
a t that time.
Tnese occurrences are not expected to be many and are expecte:
to result in only minor changes to an inservice ins;e: tion or testing progran All relief fecm AE1E Code retuirements that are deterr.ined to be impractical f or a f acili t;. will be grantec in the form of a letter within the provisions of 150.55a(g)(5)(i).
This written relief shoulc be in:orporated into the If"""
, document describin; the inservice inspection anc testing progran retained
, ___ )y _th e. l i c e n s e e.
Nc ti ce of_the. gra nti nc,o'f feli e f..f r.on ASME. Code requi re-r e.r, ts wi. L b_:
uti,i snee in _the FECE;AL REGISTER, but..tne. w.r.itieri relief
__. itself will n:t be:: e an explicit part of tne facility lic6ns.a or th:
Technical 5:eci ficatiens.
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INFORi% TION RECCIRED FOR fiRC REVIEW i
,0F INSERVICE INSPECTJON AND TESTING PROGRP.5 s
1.
Inservice Inspection Programs:
The infor-nation submitted for NRC review should include *, as a minimum:
Identification of the a;plicable ASME Sciler and Pressure Yessel a.
Code Edition and Addenca The period for which tne program is applicable b.
Identification of all of the s;ecific con:enents and' parts to be examined for each A5:iE Ccce Class (i.e., each Quality Group as defined c.
in Regulatory Guice 1.26, "Cuality Group Classi ficanons and Standards and Radioactive-tlaste-C:ntaining Components of Steam fo r 'da te r Power Plants"), and the inspectico intervals for each Class Nuclear or Quality G cup d.
For each specific component and part; specification of:
i) The exarination catagory.as defined in ASME Section XI g
p ii) The exanination method to be used iii) The epeir requirements 2.
Fump and Valve Testing Programs The informatico submitted for NRC review should include *, as a minimum:
Identification of the applicable ASME Code Edition and Addenba a.
b.
The peried for which the program is applicable -
c.
For Pump Testing: identi fy:
1) each pu"; to be test 2d (name and number) ii) the test parameters that will be measured iii) the test intervals, i.e., monthly curing operation, only during col d shutdo-n, e tc,
' Specific written relief frem the llRC is required to exclude any ASME Section X:
I;g.]
Code requirements, 03 ? ":."&
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d.
For Yalve Tes ting; identi fy:
each velva in A5t!C Section X: Categories A & B that will be 1)~ exer:ised every 3 montns curing nomal plant operation (indicate whether partial or full stroke exercise).
sa:S velve in A5:tE Section XI Category A that will be leak tested ii) during refueling outages.
all valves in A5ttE Secti0n XI Categories C, D. and E, that will clii)
For check be tested, the type of test and the test frecuency.
valves, identify tncse tnat will be exercised every 3 m:nths and those that will only be exercised during cold shutcown.,
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APjiliDIX 3 g-e r
INr00'iT10N REQUI:E0 FC: fFC REVIEU CF :10 VESTS FOR RELIEF F20"
~AS'J CODE SEciloa x1 RE0J.RE::Enis DET ERH..E2 TO BE IPP?.ACilC AL 1.
Identify cor.penent for which relief is requested:
. a.
Name and nu.ter as given in FSAR b.
Function c.
ASME Section Ill Code Class s-For valve testing, also specify the ASME Section XI valve category es d.
defined in IWV-2000.
Specifically ident fy the ASME Code requirement that has been determined to i
2.
be impractical for component.
3.
Provide inf:- atien to su;; ort the determination tr.at the retuirement in (2) is impracti:al; i.e., state and ex iain tne basis for requesting relief.
4.
Specify the inservice ins:ection (or testin.c) that will be performed in lieu
- of the A5"E Ccds Secticn XI requirements inat have been cetermined to be
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imprac ti c al.
k 5.
Provide the schedule for impicmentation of the procedure (s) in (4) above.
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h'R STAFF G'J10ELINES FO "EICLU6D:G EXEEEISING T
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(CICL ica ) TE9 5 CF Ci;.iait, v.ei5 DURil!G O NI C?i;;TiU_'_,
f ditic Any valve which when exercised (cycled) could put the plant in a Below are some examples of the types of valves that s tests during plant op. ation*:
should not be teste:.
be specifically ex:ludec from exercising (cycling) ling All valves nose f ailure in a non-conservative position curing the cyc ised. Yalves test woul0 cause a loss of system function should not be exer:
1.
l s in lines woulo typically include all non-recuncant va ve such as a sin;1e dis:herge line frcm the refueling w
' in thi s ca te;:r Other valves may f all into this or a::umul a ter and tne H:;l cu o cischarge in Ba'R's.
For certain system configurations or plant coerating medes.
example, when tre train of a recuncant system suen as ECC5 catego y untec their non-reduncant valves in the remaining train sn;uld not be cycled
.l failure culd c3use a loss of total system fun:ti'*.
s All valves, whose f ailure to close durina a cycling test would re l
Yalves in nis category would typically gamed 2.
loss of containment integrity.inciuce eil.11,es in containment p l
is open and inaperable.
a system to pressures in exces-All v al v es, which w*en cycled, 'ccul d subj e:It is assumed for the pur 3.
of their design traesures.more of the upstream che:k valves has f ailed l
methods are availaole fur cetermining the pressure or lack the that one or Yalves in this category hich pressure side of the valve to be cycled.
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would typi: ally in:!ude the isolation valves of tn
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- All A5?lE Section XI Category A and B valves should be cycled, e
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at each cold shutdown, but need not be cycled nore of ten than o months.
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ENCLOSURE 3 r-e NRC STAFF CCF"ENT3 CN INSERVICE FL:'; AND VALVE TESTING PROC?MS A'O n :,. I.. - -,,; d..e
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The NRC staff, after reviawi9; a num er of ;uma and vcive tasting programs, has cetermined that fur-her guidance mign: be helpful to illustra:e the type and ex:En: cf inf:rmation we f:el is necessary to expedite the review of these prcgrams.
We feel tr.at the Licensee can, by incor; crating these guidelines into each program submittal, reduce cen:iderably the staff's review tima and time s;ent by the Licensee in resp:nding to NRC staff requests for additional informatien.
The pum: testing program sncuid include all safety relatec' Class 1, 2 and 3 pum;s uni:n are installed in water c:: led nuclear powar plants and which a e pr:vided with an emargency ; wer 5:urce.
The vr!ve testing pr: gram sneule include all the safety related valves in the felicwin; systems excluding valves used f:r cperating convenien:e cnly, such as manual vent, drain, instrument and tes: valves, and valves used for mainten:nce only.
' PER a.
High Pressurt Inje::icn System b.
Low Pressure Injection System c.
Accumula r Systems d.
Centainren-5: ray Systam e.
Primary and Secondary System Safety and Relief Valves f.
Auxiliary Tee 64ater Systems
' g.
Reacter Building C:oling System
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Active C:r.; nents in Service Water and Instremen: Air Systems which are recuired t: su; pert safety systam functices, i.
Containmen: It:12 icn Valves required to change positica :: isolate c ntainment, p7n n.
j.
Chemical & Volume Centrol Systen y.
k.
Other key ccm:enentsrin Auxiliary. Systems which are required to dire::ly succc-t plant shutdet.n er safety system fuhetien.
' Safety related - necessary to safely shut d:wn the plant and mitigate the c:nsequen:cs of an accident.
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Residual Heat Rem val System m.
Reacter C: clan: System C'4R a.
High Press:re Cere Injectica Sys m b.
Lcw Pressure Core Infecticn System Residual H2at Removal System (Shutdown C cling System) c.
d.
E ergency C ndenser System (Isolation Ccndenser System) e.
Low Pressure C:re Spray System f.
Centainment 5:rry System g.
Safety, Relief, and Safety / Relief Valves h.
PCIC (React:r Core Isolatien Cc: ling) System i.
Contairment C: cling System j.
Ccatairment is latien valves recuired to change position to isolate containment
.k.
Standby liquid ::ntrei system (Boren System) 1.
Aut:matic De:ressurizatien System (any pilot or c:nt 01 valves, associatac hydraulic cr :neumatic systems, etc.)
m.
Centr:1 Red Drive Hydrauli: System (" Scram"functien) n.
Other key c:m::nents in Auxiliary Systems which are required to directif su : rt plant shutd:'.,n er safety :ystem functi:n.
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c.
React:r C::iant system d
' g g lg Inservice Pu and Valve Testinc Pr cram I.
Infor a icn required for MRC Staff Review of the Pump and Valve lesting Pr: gram A.
Three sets of FaID's, which include all of the systems listed above, wiEh the c:de class and system boundaries clearly marked.
The drawings should include all of the components present at the time of submittal and a legend of t.je P&ID sy :cis.
B.
Identificatien of the applicable ASPE Ccde Editi:n and Adcenda C.
The peried for which the program is applicable.
D.
Identify the component code class.
,3 _
. E.
For Pum; testing:
Identify 1.
Each pump recaired to be tested (nam act num::r)
- 2.
The test parameters to be measursd 3.
The test frequency F.
For valve testing:
Identify 1.
Ec:h valve in ASME Section XI Categories A & 5 that will be exercised every three months during normai plant operatien (indicate whether partial or full s reke exercise, and fer power Operated valves list the limitir., value for str:ke time.)
2.
Each valve in ASME Secti:n XI Category A that will be leak,
tested during refueling cutages (Indicate the leak test pr :edure ycu intend to use) 3.
Each valve in ASME Section XI Categ: ries C, D and E that will be tested, the type of test and the test frequency.
For check valvas, identify these that will be exercised every 3 months and those that will enly be exercised during cold shutdown er refueling cutages.
II. Additi:nal Inf:r aticn That Will Be Helpful in Speeding Up the Pevieu Process A.'
Include the valve 1ccatien c:crdinates or other a:propriate location infer:,.atica which will ex;edite our locating the valves on the P& ids.
B.
Provide PLID drawings that are large and clear encugh :: be read easily.
C.
Identify v11ves that are provided with ar. interlock to other ccmcenents and a brief description of that function.
Relief Recuests fr-Secticn XI Recuirtments The largest area of concern for the f RC staff, in the review of an inservice valve and pum; testing pr: gram, is,in evaluating the basis fcr justifying r lief fem sectica XI Requirements.
It has baan our ex::erience" e
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4-that many re;uests f:r relief, submitted in these programs, do not provide adequate descri::ise and detailed technical informati:n.
This explicit information is recessary to provide reasonatla assurar.ce that the burden imposed en the licensee in c mplying with the cede requirements is not justified by the increased level of safety cbtained.
Relief requests which are submittsd with a justification such as
" Impractical", "Inae:essible", or any other categorical basis, will require additional informati:n, as illustrated in the enclosed examples, := alicw The intentien of cur staff to make an evaluation of that relief request.
this guidanc: is to illustrate the conten: and extent of informatica required by the NRC staff, in the request for relief, to raake a prcper evaluatien dnd adequately d:cunent the basis fCr that relief in cur safety CVal'Vatica The NFC staff fasis that by receiving this informati:n in the re pert.
program submittal, subsequent requests for additional information and delays in c:mpleting cur review can be c:nsidarably raduced cr eliminated.
I.
Infer ati:n Recuir d for NEC feview of Eelief Recu:2_ t s A.
Identify c:m;cnent for wnich relief is requestec:
1.
Name and number as given in FSAR 2.
Function 3.
ASMS Section III Code Class 4
Fcr valve testing, also specify the ASMS Section XI valve categ0ry as defined in IWV-20C0 8.
5:ecifically identify the ASME Ccce re;uirement that has been determired to be impractical for each c:m; nont.
C.
Provide informatien to sup:crt the determination that the recuirement in (3) is impractical; i.e., state and explain the basis'for recuesting relief.
D.
Specify the inservice testing that will be perferned in lieu cf the ASPS Code Secticn XI re;uirer. ants.
Provide the schedule for implementaticn of the precedurm(s)
E.
s in (D).
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Examples to Illustrat: Several Possible Areas Where Relief May E2 Granted and the Extent and Content cf Informaticn Necessary to Make An Evaluatica A.
Accessibility: The regulatica spacifically grants relief frcm the code requirement because of insufficient acces; pre-Mcwever, a detailed discussicn of actual physical visions.
arrangerent of the ccmpenent in questien to illustrate the insufficiency of space for conducting the required test is necessary.
Discuss in detail the physical arrangement of the ccmpenent jn questien to demonstrate that there is not sufficient space to perform the code required insarvice testing.
What alt'ernative surveill'ance deans wdich will provide an'
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acceptable level of safety have you considered and why are these rears not feasible?
Envircnmental COnditiens (e.g., High radiatica level, High B.
temperature, High humidity, etc.)
Althcugh it is prudent tc caintain occupaticn *adiatica ex;csure for'inspectica peesennel as icw as practicable, the request fer relief frcm the code requirements cannet be granted solely en the basis cf high radiatien levels alene.
A balanced judgment
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between the hardships and ccmpensating increase in the level of safety should be carefully established.
If the health and safety of the public dictates the necessity of inservice testing, alternative means or even decentamination of the plant if necessary shculd be prcvided er develc;2d.
Provide addi:icnal informatien regarding the radiation levels at the required test location. What alternative testidg technicues which will previde an acceptacle level of assurance cf the integrity of the ccmpenent in questien have ycu considered and*
why are these techniques determined to be impractical?
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6 C.
Instrum ntation is not criginally previded Provide infornti:n to justify that c:epliance with the ccda requirement; would result in undue burden er hardsnips with:ut a c r.'ensating increase in the level of plant safety. What alternative testing methods which will previce an acceptacle level of safety have you c:nsidered and why are these me: hods determined to be impractical?
D.
Va tve Cycling During Plant Operation Could Put the Plant in an Unsafe C:ndition Th3 licensee sh:uld explain in detail why exercising tests -
durin; plant c:eration could jeopardize the plant safety.
E.
Valve Testing at Cold Shutdcun er Refueling Intervals :n lieu of the 3 Month Required Interval The licensee shculd exclain in cetail wny each valve cannet be exercised during ncemal operat,icn.
Also, f0r the valves where a refueling interval is indicata? explain in detail wny eacn valve cannet be exercised during cold shuttown intervals.
!!1 Accestance Criteria for Relief R2 ves:
The Licensee must suc:essfully demonstrate that:
1.
Com:liance with the cede requirements wculd result in hardships or unusual difficulties without a com;ensating increase in tne level of safety and conc:::liance will provide an ac:eptacle level of quality and safety, or 2.
Fr: posed alternatives to the code requirements or porti:ns thereof will pr: vide an ac:eptable level of quality and safety.
Standard For a__
A standard f:reat, fer the valve pertien of the pum: and valve testing program and relief requests, is incluced as an attachment to this Guidan:e.
s The NRC staff believes tnat tnis standard format will reduce the time spe,at,
by both the staff in our review and by the licensee in their preparation
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- of'the pur: and valve testing program and submittals. The standard fon at includes exar:les of relief requ-ests whicn are intended to illustrate the applica:icn of the standard for-.at anc are not necessarily a specific plar relief request.
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C Class:
3 Functicn:
Freven; backficw from the reactor ccolan: pump ccoling coils Test Raquiremert: Exercise valve for operability every three men:hs Basis for reliaf To test this valve wcuid require interruptien of cooling water to the reactor ecolant pumps co:cr cooling coils. This accion could result in damage to the reac cr coolanc pungs and thus place tr.e plant in an casafe mode of oceration.
Alternative This valve will be exercised for operability Testing:
during cold shutdowns.
2.
Yalva:
834 Category:
B-:
Class:
3 Functien:
Isolate the primary water frca the ccepenent cooling surge tank during clant operatien.
It is normally in the cicsed pcsitien, but reutine cperatien of this valve will cccur.during refueling and cold shutdcwns.
Test Requirement: Exercise valva (full scroke) for cperability eve ry th ree (3) mcn ths.
Basis for 7.elief: This valve is not required to change ;csitice during plant c;eratien to accccclish its safc:y functien.
Exercising tnis valve will inc.* ease cre possibility of surge tankline contaminatien.
Alternate Verify and record valve positica before and Testing:
and after each valve. cperatien.
s,1,,
c
- - _. ~,
s s
s-7,
/
2
.(.i....
/,4 C.,.o.r.._...,
n Class:
2 Functice-Isolate the resid'.al neat exchangers frem tne c:1 leg R.C.S. b5:P.fi w and cc:umula: ice backfles.
e s *. R s,.. i. 3... sa r -. e 2.,. *. l a..a '.<. a 3
- a. e.
-a i
.2..
Basis f:r This valve is lees:ed in a high radia:icn field Relief-(2000 mr/hr) which w uld cake the requ red sea leakage tes: ha:ardous to test personne.l. We intend :n s2=: leak te:: two other vcives (3?55 and 5755,' wnich are in :eries wi:n this v&lv:
and v.ill aisc preven: b e.:k fi cw. We feel :na:
by coc: lying with the seat leakage recuf rements v.= will not achieve a c:c:en:a::ry increase in the level of safety.
Alternative h'o alterna:ive sea; is:k testing is proposed.
Te s tin g:
e 0
wi 1
J e
e cq 4 r <)'
swu
O ENCLOSURE 4 i
D!ITE.,0 STAlh5 WUCLEAR FiGULUORY CJ:1I53Ia1 COCKET r;O. 50-320 t1gpipLITAti EDISCd CG4 PRE
_1 JEPSEY CENTRAL 10.ER & LIGHT CCMPRJ F5 GSYLVANIA ELECTP.IC CCMPA:2 MTICL Ci GP!iTfIdG OF RELILE FPGi ASMC SCC"' ION XI INSLR/1CL IilSPECTIa3 ( TC61'ING) FR OIRE.W TS The U. S. Plucleer Rigulatory Ccmission (the Comnission) has granted relief from certain r~piretrents of the AS9.S Code,Section XI, " Rules for inner ; ice Insp2ction of 71uclear Power Plant Comecnents" to the Metropolitan Etiison Corgany. The relief relates to the inservice testing program for th? Three Mile Is!cn:1 (!uclear Station, Unit 2 (tne facility), located in Oauchin County, Pennrylvania. 'Ihe ASME Ccde requirements are incorporated by reference into the Comnission's rules and regulations in 10 CFR Part 50.
Tne relief i:; et fective as of its date of issuance.
Pelief is grantml until tne start of cc:raercial operation from compliance with certain insarvice testing require rents determined to be impractical for die f acility because compliance would result in hardships and unusual dif ficulties without a cccpensating increase in the level of quality or safety.
The request for rel.ief complies with the standards and requirements of the Atomic Energy Act of 1954, as amenced (the Act), and tne Co:anission's rules and regulation.m. Tne Comnission has made appropriate findings as required by the Act and the Coamission's rules and regulaticns in 10 CFR Chapter I, which arn set forth in the letter granting relief. Prior public notice of this action was not required since the granting of tnis relief
- g e n, k
. from ASME Cecie requim: tents does not involve a significant ha:ard; ccmideration.
The Ceranission has determined that the granting of tnis relief will not result in any significant environmental impact and that pursuant to 10 CFR S51.5(d)(4) an environmental impact statement or negative declara-tion and environmental impact appraisal need not be prepared in connection with this actien.
For fur rher ti.vails with respect to this action, see (1) the letter f too the Metto@litan LMison Company dated January 3,1978, and (2) the Comaission's letter tn the lietropolitan Edison Company cated March 29, 1978.
Ihese itvas are available for public inspection at the Com.nission's Puolic Documen t Pom,17 L 7 H street, N. W., Washington, D. C. anc at the 3 tats Licrary of Pernc,ylvania, Cccracnwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
Datec at Bethesis, flaryland this 21th day of April 197d.
FOR TdE NUCLEAR REGULA? CRY CCK4ISSICH CliI:31sipsiby l
F*u A. Var;a Steven A. Varga, Chief Licot Water Reactors Brancn 4 Division of Project Managemnt i
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