ML18087A948

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Forwards Final SER on SEP Topic VI-10.A, Testing of Reactor Trip Sys & Esfs,Including Response Time Testing. Changes to Tech Specs for Surveillance Testing & Hardware Provisions Recommended
ML18087A948
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/03/1982
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO.
References
TASK-06-10.A, TASK-6-10.A, TASK-RR LSO5-82-12-009, LSO5-82-12-9, NUDOCS 8212070102
Download: ML18087A948 (4)
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Text

  • ~ ----imcket,., >. 50-213.

LSOS-82.-12-009 Hr. W. G. Couns11, V1ce Pres1dent Nuelear Eng1neer1ng and Operations

. Connecticut Yankee Atanic Power Co.

Post Office Box 270 Hartford, Connecticut 06101

Dear Hr. Couns11:

SUBJECT:

SE~ TOPIC VI-10.A, TESTit<

Etkitr;EEREO SAFETY FEATURES* IHCLUDI HG. RESPONSE TIME TESTIHG - FINAL SAFITT EVALUATIOH REPORT FOR THE HADDAM HECK PLAKT Enclosed is the staff's f1nal safety evaluation report {SER). Our SER is based on our contractor's technical evaluation which was provided to you in a letter from O. M. Crutchfield to W. G. Couns1l, dated July 22, l9C2 (and which became final 30 days later) and the add.1t1ona1 1nfor.-:-.a-t1on provided 1n a letter from w.* G. Oouns11 and J. P. C4'gnetta to O. M. Crutchfield, dated NovE!'i'lber 8, 1982.

The staff continues to reccxrrnend changes 1n t~ Technical S::>e<:1f1cat1ons for surveillance -tes t1ng and the prov1sfor. of *"hardware for re-sponse time testing. This evaluation w111 be a basic input to the int~rated p1ant safety asscs~ent for your fac111ty.

The assessment fnGJ be revised in c

.J the future 1f your f~c1lity design 1s changed or 1f NRC criterh re1at1r.g St;C' to this topic are mod1_f1ed before the integrated a~ses~.ent is ccr.:;J1e~ed.

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Enclosure:

As stated cc w/enc1osure:

See next page 821207010~ 8~1203 PDR ADOCK 05000213 Sincerely, Dennis M. Crutchfield, Ch1ef Operat1no Reactors Branch "°* 5 01vis1on-of L1c~s1ng p

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SYSTEMATIC EVALUATICH PROGRAM TOPICrVI-10.A

/.

HADDAM NECK PLANT TOPIC:

VI-10.A_, __ J_esting of Reactor Trip System and Engineered Safety Features, Including Response Time Testing I.

TI.

II I.

. INTRODUCTION The pL..*pose of this topic is to revie~ the reactor trip system (RTS) and engineered safety features (ESF) tjst program for verification of

~TS and ESF operability on a oeriodic basis and to verify RTS and ESF response time in order to assure that operability of the RTS and ESF.

Response times should not exceed thosP *-.urned in the plant accident analyses.

Accordingly, the test program of the RTS and ESF was revie-.ved in accordance with the Standard Review Plan, including ~pplicable Branch Technica 1 Positions.

  • REV! EW CRITERIA The review criteria are presented in Sect;on 2 of EG&G Report 0043J, "Test.ing of Reactor Trip System and Engineered Safety Features."

RELATED SAFETY TOPICS AND INTERFA<<S._

Topic VI-7.A.3 discusses the question of testing engineered safety features systems under conditions as close to design conditicn as practical.

There are no topics ~hat are dependent on the pres@nt topic infonnation for tbefr' completion.

IV.. REVIEW GUIDELINES Review guidelines are presented in Sec.tio:'l 3 of EG&G Report 0043J.

V.

EVALUATIO~

The 1-taddam Neck design is evaluated against the review criteria in Section 3.2 and 4*.2 of the EG&G report and additional 1nfonr.ation was.

provided by the licensee in a letter from W.G.. Counsil and J.P. Cagnetta to O.M. Crutchfield, dated November 8, 1982.

ihe identified differences from current re~iew c~iteria as follo~s:

1.

The RPS is not tested for automatic or manual acti.Jatfon during reactor operatic~, however, the variable lo~ press~rizer trip calculator is tested every six weeks.

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Section 4. 1 of the Haddam Neck Technical Specifications tirovides the surveillance requirements for the RPS.

Table 4.2-1 provides the surveillance schedu*les for RPS instrumentation.

3*.

The Manual trip, the Pressurizer low Pressure trip, -and ~he Hig_h Steam Flow Isolation Valve trip circuitry are not included for

~esting, calibration, and channel checks. These parameters-do not.

apo~ar in T*ble 4.2-1 of Section 4.2 of the lechnical Specifications yet they are identified as_ part of the RPS elsewhere in the Techni*-

cal Specifications.

Testing of the manual trip circuitry during reactor operation wou1d result in a reactor trip.

Therefo~e. this test is only conducted during.

start-up in accordance with operating procedures

  • The pressurizer pressure channel 1s included in Table.4.2-1 of.the Technical Specification~. although this is not listed.in Table 4.2-1 as "Pressurizer Low Press 1Jre," but rather as "Pres5urizer Pressure.

11 This channel is required to be checked, ca1ibrated, and functionally tested as stated th.Table 1.

A channel check, *calibration, ijnd functional test fo~ the hig~ steam flow

. i~olation valve trip (also referred to as the main steam line i~olation valve trip} are not required by the Technical Specifications, however, these tests are conducted in accordanee with plant operating procedures as stated in Tabl~*l.

4.

The testing, calibration, and channel check requirerrients set forth in Table 4.2-1. Section 4.2, of the Haddam Neck Techn 4:al Specifications include testing ~nd*channel checks for Intermediate Range Neutron Flux and Reactor Coolant Temperature.

These two parameters are not identi-fied as part of the. Haddam Neck RPS.but they are identifierl as RPS in

. the Standard Technic~l Specifications.

This is one example of a discreoancy in the design documentatio~ of Haddam Neck.

Other discrepancies that are identified by our contractor are in-volved with a ceomparison of ltens A through F in the EG&G report.

Such a comparisM indicates-differences as to what parameters constitute ttle Haddam Neck RP~ and made it difficult to conduct an independent safety review.

ra*resol~e the staff's concerns, the license~ ha$ identified the instruments that initiate reactor trip (Table A) and enoineered safety features (Table B).

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The TE>>chnica 1 Spec if icat ions do not *r~uire channel funct 1ona 1 test fog tor ___ the Steam-Ft.'edwat.. ~r Flow Mismatch anJ tow Steam *Generator

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Pio functionc:d test is perfonned on the Ste;,1'!"-feedwater Flow Mismatch and low Stea,.. Generato'r ~ater Level channe since these are arranged

n a 1/t *mafrix.

~ funi:tional test wouJd. therefore. result in a reactor trip.

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1he Ha1dar.'! Nec:k Technical SpecificaUons do not estahlish Response Ti~e Testing.for the RPS.

7.

yhe ~ajda~ Nee~ Technical Specifications establish surveillance re-q1..drAr.ents fer the ESr systef'ls a!'.. stated 1n Ta.ble 2.

Surveillance requ;reMents for the instrument channels.and actuated equipmP.nt as-sociated ~ith the Engineered S~fety Features Systrms can be found in

~able-4.2-1 and Section 4.3;

!t is the staff'~ position that the design of systems which are requ.ire~

~-:.,. *)afe-ty shall.incl1.1:Je pro*.dsions fol"--periodic verification that the

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perfomance of instru:rents and control is not less than that

~~:~~ i~ in the safety analyses.

The bases* for this position are Gener~l

~esig~ Criteria~ 21~ Settion 3.9 of IEEE Std. 279-1971. and IEEE Std. 383-1'371.

Therefore, the licensee should ;mplemen*~ a program for testing and

(;a1itratin;.;11 n:-act~ protei:ticn systems (incltidino engin\\.ered*safety fea~"re:, S'.fS~~s ~uc~ as contaiment isolation).

As a part of this 'program.

t... f..- re<;u.r.::f' t~r-f tE-:.t requirer.;ents should be stated in the T~chninl Speci-

.f,(a~io~~ i~*a *manner si~ilar to that of th~ Standard Technical Specifica-tio~s.

I~ ~ddi~icn. test and calibrat1on frequencies similar to that of the

~tar~~r~ ~E'chr.ical Specifications snould be used unless sane other frequency c~~ bt e~!a~li~hed on a well defined technical basis.

r~e ~ta'f pr~po,es that the f611owing corrections be made to existin9

~ro;r3~~ t1 ~a~i.n~ ~uitable change~ in the Haddam Neck procedures and Te~~ri~al Spe~ifications:

T**~ license~ ~hould provide for channel checks.of Steam Flow Channels in

~~E.- T<::-thnital Spectrications.

2.
~i:: li'..E.-r,*,<::-e,.,.,otild design, pr*:>\\lide suitable test equipment for. ~nd.

,_,u~~~~ ~~r'~~~r: re*,;...(.r*;.f' tir*e te:.t~ of those-'hannels and systems that

~r~ r~~ 1;r~1 '0' t~e protection of public health ~nd safety..

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