ML17194A146

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Forwards Request for Addl Info Re Proposed Tech Spec Changes to Provide Surveillance Requirements for Scram Discharge Vol Vent & Drain Valves.Addl Info Requested within 45 Days of Receipt of Ltr
ML17194A146
Person / Time
Site: Dresden  
Issue date: 09/02/1981
From: Ippolito T
Office of Nuclear Reactor Regulation
To: Delgeorge L
COMMONWEALTH EDISON CO.
References
NUDOCS 8109160014
Download: ML17194A146 (9)
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Docket Nos. 50-237 and 50-249 Mr. L.O. De1George Director. of Nuclear Licensing Comrnqnweq~*th Edison Company P.O. Box 767 Ch~~ago~ Illinois 60690

Dear Mr. Del George:

SEP 2 1981 Dis~bution

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By letter dated July 7, 1980,*we r~quested that you propose Technical Specification changes for Dresden Units 2 and 3 to provide surven 1 ance requirement's* for scram discharge volume (SDV} vent and drain valves and LCO/

Our consultant, Franklin Research Center (FRC}, has reviewed your submittal in respqnse to *this letter and has identified the need for additional informa-tion.

We have eva 1 uated the FRC document and agree that this in format ion is needed in order to complete our'review.

Accordingly, please provide the a~ditional information requested in the enclosure within forty-five (45} days of your receipt of this letter.

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If you or your staff have any questions on this matter, please contact your project manager.

Enclosure:

Request for Additional Information cc: See next page w/enclosure Sincerely,

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'.I:. A. ippoiiU>

Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing 8109160014 8'10902 t PDR ADOCK 05000237 *

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NRC FOFlM 318 (10-80) NRCM 0240 OFFICIAL R~CORD COPY USGPO: 1981-33$-960

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Mr. L. DelGeorqe*

cc:

Mr.* Phi 1 i p Steptoe*

Isham, Ltncoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603

-Mr. Douglas Scott=-

Plant Superint~ndent Dresden Nuclear Power Station Rural Route #1 Morris~ Illinois. 60450 Morris Public Library 6Q4 Liberty Street

. Morris, Illinois 60451 U. S. Nuclear Regulatory Commission Resident Inspector's Office.

  • Dresden Station RR #1.
    • Morris, Illinois 60450 Mary Jo Murray, Esq.

Assistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chic~go, Illinois 60601 Natural Resources Defense Council 917 15th Street, fi.W.

Washin*gton, D.C.. 20005 Chairman S-Oard of Supervisors of Grundy County Grundy County Courthouse Morri's, I1 lino is* 60450

. rtli"nois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Sprtng~teld, Illinois 62704 U~S: Environmental Protection Agency Federal Activities Branch Regton V Of fi"ce Attn:

Regfonal Radiation Representative 23Q. s*outft Dear5or11 Street Cfttcago, Tl 1 ino ts 60604

.. Tfte Honorable Tom Corcoran*

  • United States House of Representatives wasl'i5ngton, D~C. 20.515.

John F. Wolf, Esq. *

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  • 3409 Shepherd Street Chevy Chase, Maryl and 20015 or; Linda W. LittTa SQQ Hermitage Driv~

Raleigh,' North Carolina. 27612 Dr.. Forrest: J. Remfck 305 East Hamilto~ Avenue State College, Pennsylvania 16801 Mr. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station

  • Rural Route* #T Morris.,. Illinois 60450-

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. REQUEST FOR ADDITIONAL. INFORMATION.*

~ BWR SCRAM. DISCHARGE VOLUM.E..

~-LO [\\J G-TERI\\1 rvro DI FIC'ATION*s:

  • . COMMONWEA.LTH ED I SON COMPANY
  • DRESDEN NUCLEAR POWER STATION UNITS z*AND 3 NRC DOCKET NO:

50:-237, 50-249 NRC TAC NO *. 42213, 42226..

~nklin..Research Center

. A:. Division of.The Franklin Institute The Senjemin Franklin Parkway. Phila~ P&. 19103 (215) 448*1000~.

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BACKt;ROtJNO This Request. for Additional Information. (RFI) is the result of* an-evaluation of information con~ained in* a letter. dated October 14, 1980 from-Corr.monwealth Edison, One First National Plaza:, Chicago, Illinois 60696. to the Nuclear Regulatory Commission (NRC) in response. to NRC' s request for Technical Specifications. changes.. regarding Dr:escen Nuclear. Power Stat~on. Units 2 and 3 surveillance requirements for scram discharge volume (SDV) vent and drain valves, and limiting conditions for operation* (LCO)/surveillance requirements.*

'for reactor protectiOn system (RPS) and con.trol. rod block SJ;>V limit switches *.

The evaluation was* made in accordance.,.ith criteria contained in the Model Technical Specifications proposed' by NRC staff and incorporated into the*

_General Ele_ctric Standard Techn~cal Specifications.

The evaluation revealed three items of conce~ to which unsatisfactory.*

re~pdrises~.~ere* obtained. _One i tern of concern refers to surveiilance*

requirements *for s.ov drain and: v~nt valves; another item e>f concern refers to* -

.LCO/surveillance requirements for reacto.r protection* system SOV limit*

's.,.itches; and_ a-third item of concern refers_to LCO/surveillance requirements for control rod block sov* limit switches.

  • 1>.dditional_ information related to these items of concern is needed before a final evaluation of* the* proposed Technical Specifications changes for*

Dresden -Nuclear_ Power Stat'i'on uni ts 2 and 3....c.an be-made.*

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.e REQUEsrEo CHANGES IN TECHNICAL SP'OCIFICATioNS The changes _in Technical Specifications involve surveillance requirements.

of the main components and' instrumentation of: the scram discharge volume.

They cover thr~e areas of concern, as described below *.

I.

  • Surveillance. Recu irements for SDV Ora in and Vent Valves The surveillance.requirements of the Model Technical Specifications for snv dra~n and vent valves are:

_"4.l.3.l.l -*The scram discharge volume* drain and vent va~ves _shall be.

demonstrated OPERABLE. at least once per 31 day_s b::f.:

a *. Verifying each valve* to be open*~, and b *. Cycling each valve at. least 'one complete cycle of. full travel.

"*These valves may be closed in~er_mi ttently for testing* under.

administrati~e controls.*

coininOnweal th Edison's response to the above surveillance requ ire!Tlents.. for.

SDV dra.in and* vent valves. is given in the subsequent paragraph:'..

"3.

The scram discharge volu~e vent and drain val~es shall be verified open at least once per. 31 days.

These valves may be closed intermittently for testing under adminsitrative control.

At leas*t once each Re~~eiing Outage, the scram discharg~ volume vent~nd drain: valves.will be dernon~trated to:

CONCERN*

a.* C_lose within.15 *seconds* after receipt of a signal for control rods.. *to scram, and

. b. Open when* the* scram* signal is reset.**

ITEM l Commonwealth Edison's* response in paragraph 3. does not contain the:

requirement of the Medel Technical Specifications of parapraph 4. l.3. l.lb to

!J *.U Fran~n Reseuc:h Center

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cycle.', each. varve,- a.t.; lea* st one*.':comp.le.te.. *' cv.~!e:. of"" full.-. trave1**

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.at, least. once:* pet.*

31 days *.

REQUEST Provide technical bas~s why.the requested change is not appHcable* to Dres.oen* Nuclear Power Station: units 2 and 3 9 II.~

LCO/Surveillance Recuirements for Reactor Protection System Scram Oischarae Volume Limit Switches The* required changes. in the Technical Specifica_tions with reference to LCO/surveillance requirements. for reactor protection system scram discharge vo*lume limit switches are given in th;-- NRC staff's* Model Technical Specifications a.s reproduced below.*

  • 4.3.l.l - Each reactor. protection system instrumentation channel. shall

' be deriionstrated OPERABLE by the performance of the CP.ANNEL CF.ECK'* CHANNEL

  • FUNCTIONAL TEST, and CP..ANNEL O.LIBAATIOH operations for.the OPERATIONAL CONDITIONS and at the frequef?Cies shoWn in Table 4.3~1.l-1.*

The required* information from the t~ble referred to in the abOve parag.raphs follows.

Table. 4.3.1.1-1; Reactor Protection System ~nstiumentation Surveillance* Requirements Functional

    • .Unit
8. ~cram Discha~g~.

Volume Water.'

Channel check

  • Levei!""Righ..

NA:

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~DD Fr~nklin Research Center A CM.iotl ol TM FraMJin INlitMUI*

.Channel.

  • Functional Ch~nnel

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Test

  • Calibration..

Operation.al.

C6nditions* in W~ich Surveillanee Recuired

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. CONCERN.

Referring to paragraph 4.3.l.l and Tab.le: 4-.3.1.1-1 of the Model Technical Specifications, the* Te~hnical Specifications for: Dresden Nuclear* Power Statfon

.o.nits 2 and 3* shoul.d: contain a. similar paragraph and table or. an equivalent paragraph stating that each reactor protection system scram discharge ~volume:

wat-er: level-high *instrumentation channel containing.a limit switch* shall be d~monstrated OPERABLE by the performance of the,CHANNEL FtJNcTIONAL TEST 2.!!£!

Per month and CHANNEL CALIBRATION operations each refuelling outage for ~e OPERATIONAL CONDITIONS l, 2., and S.

_REQUEST The Technical Specifications for Dresden 2 and 3 state that each reactor protection system scram.discharge volume water level-high instrumentation channel containing a limit switch shall be demonstrated OPERABLE by the per~

formance of the CHANNEL.FUNCTIONAL TEST once per 3' months,.and.there are no

  • tech specs for CHANNEL:.CALIBRATION.

since th~p~oposed frequency of the required.surveillance for.Dresden* Nuclear Power Station Units 2 and*3.differs from.the frequency requested by the Model Technical.Specifications, provide technical bases for it.

III. LCO/Surveillance Reauirements for Control* Rod* Block Scram Discharge Volume Linii t Switches

.The provisions.of the Model Technical Specifications in regard: to

  • limit switches* are:

"4.3.6.

Each of* the above required. control. rod with.drawal. bloek trJ.:*P.**

sys.terns and; instrumentation channels shall be* demonstrated. OPERABLE by*

the* per.formance~ of' the CHANNEL CHECK, CHAh"NEL FUN:TIONAL _TEST and C?.ANN£L CALIBRATION oper.ations for the OPEAATICNAL CONOITIONS and at the

  • *. frequencies shown in* Table 4. 3.6-1. **

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I The:* inforrr.ati~:m* contained:: in* the' tabl:e** referred. to in*. the> abo.ve.<

paragraph~ follows.

Table* 4.3.6-.l.

Control-Rod Withdrawal Block Instrumentation Surveillance

  • Requirements Trip Function Channel
  • Check Channel Functional Test Channel.

Calibration Operational Conditions In Which Surveillance Requ ir~d.

  • . S..

Scram Discharoe Volume*

  • a.

b

  • Water Level-High*. NA scram. Trip_

Bypassed NA.

Q R

l,2,S**

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    • With 11\\0re than one -~ontrol *r~d withdr~~n.- *!Not -appii~able to control r9ds.

reno~ed per Specification 3!9~10~1 or ~.9-.1~~2. *-:*****.: ;**

ln:M 3.

CCNC::RN.

_?.efe:riri~ to parasr!.ph 4.~*.6 E.nc Tabie ~.LE-l. cf the Hodel Technical..

  • S?e~i~ica~~c~s, ~he* T.ech:ii 0

c!.l.S?~-ificatio~s fo~: Dresden ~uc1ear :>~~*er station

  • units i and 3 should contein a simila"r pira*~!.?h-and t~ble. or ~n e<i\\livalent
r.c~ths anc.CH.i.h"l\\::L C~.l.lSF.?.TIO~* O?etHio~s ~ach ref~ell:inc ol:taoer a scum**

tii? bypas!.ei3: irist:i:;..entE.tion channel containins ~* limit: s.. d.tch s~all be.

.. ".. C:e:;.:nst:*at*e.d~*O?!~~=.!.rZ: b°'.*_*, the **:>eTforn.ance of the Ci.~~1~tL !~*-~TloN~.L TEST***

  • ... *~*~.month.,'*. For the surveillance* specified_, abO._;.e, the OPERATIONAL

.CONDITI*ONS shall.~- 1,2,S**..

. **As; in Table 4.* J:.6:-1.

Commonwealth* Edison.' s response is; contained in Table 4.2*.1 page 43: of the*..

. Technical Spe~ifications for ~resden Nuclear Power. Station Uni-ts* 2 and. 3 *.

This response*.differs' from the.-. requirements of* the Model Technical Spe<;: H ications *..

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REQUEST Provide* technical basis for not calibrating the'. scram discharg~ volume water level-high* instrumentation* channel.

Also. provide technical basis for performing the scram* trip bypassed instrumentation channel functional* test*

  • once per refueling outage instead of once per month as requested in the
  • *Model Technical Specifications.

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LlUJ~ Franklin Research Center:.

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