ML17255A560

Discusses Proposals Received to Fulfill Regulatory Requirement Re Installation of Reactor Vessel Water Level Sys,In Response to Generic Ltr 83-12, Inadequate Core Cooling Instrumentation Sys.

ML17255A560
Person / Time
Site:	Ginna
Issue date:	11/29/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-12, NUDOCS 8312090166
Download: ML17255A560 (8)

Text

'REGULATORY =INFORMATION DISTRIBUTION SYSTEM (RIDS)

'ACCESSION NBR;8312090166'OC DATE; 83/11/29 NOTAR EO; NO .

244 Robert

~

Emmet>> Ginna>> Nuc1.ear P 1 ant i Uni,t ii Rochester>> G 05000244 DOCKETACIL:50 AUTH NAME'UTHOR AFFILIATION MAIERiJ,E ~ 'Rochester Gas 8 <<ElectriC, Corp,,

'RE<<CIPi NAME< RECIPIENT AFFILIATION ORUTCHFIELDiD~ Operating Reactors Br anch ,"5

SUBJECT:

Oi scusses lproposal s r eve i ved to- f ul fi 1 1 r equi a tor y r equir ement r e, instal ation 1 of reactor vessel water )evel sys in>>'r esp'onse"'.to Generic Ltr 83 12i "Inadequate Instr umentation>>>>Sys," ICore.'Cooling DISTRIBUTION 'CODE: AOOZS 'COPIES 'RECEIVED:L>>'TR

'R Submilt ta 1 Inadequate iCore>> Cool i ng. ( I tern J 'NCLSIZE:.'.ITLE I I' F j 2) 'GL 82 28

'

NOTES:NRR/DL/SEP icy, 05000244 RECIPIENT >>COPIES RECIPIENT COPIES'TTR.

ID CODE'/>>NAME<< LTTR 'ENCL' ID CODE/NAME ENCL>

NRR:ORBS'C NRR ORBS,LA

,OICKiG INTiERNAL';,NRR SHEAi J'1 NRR/DHFS/PSRB16 1-NRR/DHFS/HFEB1'5 NRR/DL/ORAB 08 1

1 NRR/OS II DIR 09-. 1 NRR/DSI/CPB 10 v

,NRR/OSI/IICSB 1' SB 13 14.'ORB5!PM 00 1-

. RGNi 07 1 EXTERNAL! ACRS NRC,,PDRI

,NTIS 17 02~

05.

1'PDR 10 1

1 NSIC'03" 06 NOTES:

lTOTAL" NUMBER"OF ICOPIES REQUIRED'TTR 31 ENCL

(" l '3) w r', ) I wi Ti I )

l R.,jhow

() "i (y w~

w )w

~'i "~<<oo

~ w

) "'~~I )t' rn i"w'ww l f 'wr Tu il, )ig ) <<'<> I <'8'> ),) A Iw w "w wt w

> ) ) Ir>>'w f QQ>~ r>nn r tfoH Lwa j-wwg ~ JI JA g

} "~,. l

> s f4 T ll jl w >

. 'r -<,')

>a nJ o ~ 0 o~ f ) 8 ~ 3 ~ 4>':wIIA )

~)r)IY~ IJIH)u O'-"At,'-) I') )'=l r'Ion6>>) p9np oig90 gn ~ ~ ~ ->J:II~HDTU~ J

~<o~rifwwpe~ f fr ) fu4 ep r"~vf9vog Bio wo+A+g gg~pQgprg I,IJf >'l'wr" l 99') l n 9') fi i l '4p pov nn 0;)~>,) 1 fn no < f 6 f l tt') dn r o'l ") n'%vie'91 r Urw'->'l

~~o) ~gruvwh(nl",4f-F~ qf ) qra~n)d of ~~nope')~ nr eg<

",eyP, nor gcPnomiwo fpnI g>n fno ) <

~WIg .)',)~id <<<TJ-'(rdqI )')34 ".iI")i).> Pbiw<>h: 3r)V ) <'j >I le>qI'wTiIw)

(5. <<. I1 .~~8 I ) gnr ion') o~o) o gE'uriobgn1: fr 9 4'l~r)<>> 8(4: 3 ) f I I

'I

>w ~

Q ~) w) ij P t) ,yet ')38%J>>'wHHA:w'l ~

T>>lqI>>A wj I wijj)g 'J)"3

~>T L .l wj )A iih -f "!) ) nI

><Hi';)i, 3 n)TJ h J t.,~'v<ww r A.)<'2 ><Ad); JA )R~T<') I oI w',.<c" ~%89'4c)X~'jhow)

(f) HIV 18<)X~H>>

iI I

>>rl') it X BVX)wj~'~j Iu e~H-pwe ~~r) >.f f P~<QA: )A,IH 9 f'X3 c) w! 3 I >t" l J'").]

t g fl Ps Tw'

It //E/$8 ///////I/Y i'////

3Z;

$ 0$ lK

/// SrnluZu ROCHESTER GAS AND ELECTRIC CORI7ORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER 7 C I. C P H 0 N C Vie PreetIent ARE* CODK 7ld 546-2700 November 29, 1983 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Inadequate Core Cooling Instrumentation System Generic Letter 82-12 R. E. Ginna Nuclear Power;,Plant Docket No. 50-244 Dear Mr.

8 Crutchfield:

1 In a 'letter dated March 10,'983, RG&E acknowledged the regulatory requirement to install a reactor vessel water level system. RG&E has received proposals from Combustion Engineering and Westinghouse for the two types of instruments generically approved by the Staff for use in PWRs for tracking reactor coolant system inventory. A proposal was also received from Technology for Energy Corporation for a gamma thermometer device. In addition, RGGE contracted with Nuclear Projects, Inc. (NPI, the SNUPPS organization) to perform an independent review and evaluation of systems for reactor coolant inventory indication.

One conclusion of the NPI study is that "existing plant instrumentation and procedures are adequate to advise operators of how to respond to voids in the reactor vessel head or distributed through the reactor coolant system." RGGEIs investigation of a differential pressure system (dp) similar to that proposed by Westinghouse and a heated junction thermocouple system (HJTC) similar to that proposed by Combustion Engineering, concluded that either system will fulfill the requirement to trend reactor coolant inventory. RG6E's evaluation of a gamma thermometer device similar to that proposed by Technology for Energy Corporation concluded that this device may, in the future, be proven to provide acceptable vessel inventory indication. It may be relatively easy to install, and it may have future application for power monitoring. Uncertainty over potential plant specific installation problems and lack of a completed equipment test and qualification program have prevented us from giving further con-sideration to this system at this time. Accordingly, the choice 83120'VOibb 83ii29 PDR ADOCK 05000244 P PDR

II I jp, W>>

C.

I'-

PI k

p li

ROCHESTER GAS ANP ELECTRIC CORP. SHEET NO.

pATE November 29, 1983 To Mr. Dennis M. Crutchfield of system to be installed is limited to those types generally approved by NRC. Because of the conclusion of the NPI study and RG&E's perceived need for a vessel inventory trending instrument, the system choice is based primarily on cost.

Two approaches have been taken to evaluate the total installed costs of the HJTC and dp systems. The first approach has been to contact utilities that have already installed one of these systems, discuss their experiences, identify particular problems, and obtain data on actual installed costs. The second approach has been to obtain firm quotations for equipment supply and other work that suppliers would perform and then to identify additional necessary work and estimate the costs of installation at Ginna.

The costs at other plants that we contacted for installing the Combustion Engineering and Westinghouse systems have ranged from more than two million dollars up to eight million dollars.

The upper range cost estimate was for a complete inadequate core cooling system package that included more than just a reactor coolant inventory monitor. Plant specific work at each site (for example, containment penetrations, and reactor vessel head modifications) makes each installation unique, however, the cost estimate for an inventory monitor at Ginna is probably inter-mediate between the two extremes.

Our plan is to install a differential pressure type instru-ment to add inventory trending to our accident monitoring capability. The system will monitor from at least the bottom of the hot leg to near the top of the head. Decisions on system details such as where the RCS attachments will be made, trans-mitter locations, tubing routing and software and display informa-tion are yet to be made. Equipment may be purchased from a single vendor (Westinghouse) or may be designed and procured by RG&E.

Vendor delivery of equipment has been quoted as eighteen months. Engineering of the system and coordination of this work with previously scheduled modifications result in an installation during the 1986 refueling outage. Final equipment and system operability testing will be performed following plant startup.

Additional information about the instrument and the installation schedule will be available as we proceed with engineering.

RG&E has in service adequate instrumentation for detection of inadequate core cooling, including subcooling margin monitors and core exit thermocouples. Redundant subcooling margin monitors to meet TMI requirements were installed in 1979 and are currently operable. RG&E also plans to upgrade the existing 39 core exit thermocouples to meet NUREG-0737 requirements. This work will be performed during the 1984 and 1985 refueling outages. The long

p P

ROCHESTER GAS AND ELECTRIC CORP.

DATE November 29, l 983 SHEET NO.

To Mr. Dennis M. Crutchfield lead time, and one of the significant cost items for this upgrade, results from the new containment penetrations necessary to support this modification. The existing core exit thermocouple configura-tion, including three thermocouples in the upper head, is expected to provide indication of upper vessel voiding for all but the most extreme containment environmental conditions which may result from LOCAs. Only large break LOCAs, which have been shown to be precluded by "leak before break" work sponsored by RGGE for the Ginna reactor coolant system, can produce the extreme environ-mental conditions which might cause the thermocouple cables to fail. Thus, sufficient indication will be available to plant operators to diagnose and mitigate potential inadequate core cooling events, prior to installation of the inventory trending device and upgrade of the core exit thermocouple.

RGSE has chosen to implement a dp type inventory trend monitor to complement our existing inadequate core cooling instru-mentation based partly on previous regulatory endorsement of this type of instrument. Please inform us of any open issues or concerns that the staff may have about this system.

Very truly yours, John E. Maier

f