ML17255A560: Difference between revisions

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| number = ML17255A560
| number = ML17255A560
| issue date = 11/29/1983
| issue date = 11/29/1983
| title = 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.
| title = 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
| author name = Maier J
| author name = Maier J
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:'REGULATORY =INFORMATION DISTRIBUTION SYSTEM                                                     (RIDS)
{{#Wiki_filter:'REGULATORY =INFORMATION DISTRIBUTION SYSTEM (RIDS)
'ACCESSION     NBR;8312090166'OC                         DATE; 83/11/29         NOTAR                           EO;   NO               .
'ACCESSION NBR;8312090166'OC
244 Robert
~ DATE; 83/11/29 NOTAR EO; NO DOCKET''ACIL:50 244 Robert Emmet>> Ginna>> Nuc1.ear P 1 ant i Uni,t ii Rochester>>
                                                          ~
G 05000244 AUTH NAME'UTHOR AFFILIATION MAIERiJ,E ~
Emmet>> Ginna>> Nuc1.ear P 1 ant               i Uni,t                           ii   Rochester>>               G 05000244 DOCKET''ACIL:50 AUTH NAME'UTHOR AFFILIATION MAIERiJ,E     ~     'Rochester Gas 8 <<ElectriC, Corp,,
'Rochester Gas 8 <<ElectriC, Corp,,
    'RE<<CIPi NAME<           RECIPIENT AFFILIATION ORUTCHFIELDiD~               Operating Reactors                   Br anch ,"5
'RE<<CIPi NAME<
RECIPIENT AFFILIATION ORUTCHFIELDiD~
Operating Reactors Br anch
,"5


==SUBJECT:==
==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
Oi scusses lproposal s r eve i ved to-ful fi 1 1
          'R     Submilt ta 1 Inadequate iCore>> Cool i ng. ( I tern J    'NCL''SIZE:.'.''ITLE I I' F j 2) 'GL 82 28 NOTES:NRR/DL/SEP         icy,                                                                                                                 05000244 RECIPIENT                       >>COPIES              RECIPIENT                                      COPIES'TTR.
r equi a tor y r equir ement r e, instal 1 ation of reactor vessel water
ID CODE'/>>NAME<<                   LTTR 'ENCL'        ID CODE/NAME                                                      ENCL>
)evel sys in>>'r esp'onse"'.to Generic Ltr 83 12i "Inadequate ICore.'Cooling Instr umentation>>>>Sys,"
NRR:ORBS'C                                           NRR  ORBS,LA
DISTRIBUTION 'CODE:
              ,OICKiG INTiERNAL';,NRR SHEAi      J'1 NRR/DHFS/PSRB16                       1-NRR/DHFS/HFEB1'5 NRR/DL/ORAB 08 1
AOOZS
1 NRR/OS II DIR 09-.                    1              NRR/DSI/CPB                               10                           v
'COPIES 'RECEIVED:L>>'TR J
              ,NRR/OSI/IICSB                        1'                              SB                       13 14.'ORB5!PM 00                1-
'NCL''SIZE:.'.''ITLE
            . RGNi              07                  1 EXTERNAL! ACRS NRC,,PDRI
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              ,NTIS 17 02~
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,NRR/OSI/IICSB 14.'ORB5!PM
. RGNi 07
>>COPIES LTTR 'ENCL' 1-1 1'
1 RECIPIENT ID CODE/NAME NRR ORBS,LA NRR/DHFS/HFEB1'5 NRR/DL/ORAB 08 NRR/DSI/CPB 10 SB 13 00 COPIES'TTR. ENCL>
1 1
v 1-EXTERNAL! ACRS NRC,,PDRI
,NTIS NOTES:
17 02~
05.
05.
1'PDR 10 1
10 1
1 NSIC'03"                                 06 NOTES:
11'PDRNSIC'03" 06 lTOTAL" NUMBER"OF ICOPIES REQUIRED'TTR 31 ENCL
lTOTAL" NUMBER"OF ICOPIES                   REQUIRED'TTR           31   ENCL


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                                                                                                      $ 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
SrnluZu 3Z;
$0$lK ROCHESTER GAS AND ELECTRIC CORI7ORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vie PreetIent 7 C I.CP H0 N C 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:==
==Subject:==
Inadequate Core Cooling Instrumentation System Generic Letter 82-12 R. E. Ginna Nuclear Power;,Plant Docket No. 50-244 Dear Mr.
Inadequate Core Cooling Instrumentation System Generic Letter 82-12 R.
8 Crutchfield:
E. Ginna Nuclear Power;,Plant Docket No. 50-244
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>>
==Dear Mr. Crutchfield:==
8 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 fulfillthe 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
 
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ROCHESTER GAS ANP ELECTRIC CORP.                                      SHEET NO.
ROCHESTER GAS ANP ELECTRIC CORP.
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.
pATE November 29, 1983 To Mr. Dennis M. Crutchfield SHEET NO.
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.
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 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.
The upper range cost estimate was for a complete inadequate core cooling system package that included more than just a reactor coolant inventory monitor.
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.
Plant specific work at each site (for
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.
: 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.
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
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


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ROCHESTER GAS AND ELECTRIC CORP.
ROCHESTER GAS AND ELECTRIC CORP.
DATE November 29,     l 983                                  SHEET NO.
DATE November 29, l983 To Mr. Dennis M. Crutchfield 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.
lead time, and one of the significant cost items for this upgrade, results from the new containment penetrations necessary to support this modification.
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.
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
Very truly yours, John E. Maier


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Latest revision as of 11:06, 8 January 2025

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 Constellation icon.png
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 DOCKETACIL:50 244 Robert Emmet>> Ginna>> Nuc1.ear P 1 ant i Uni,t ii Rochester>>

G 05000244 AUTH NAME'UTHOR AFFILIATION MAIERiJ,E ~

'Rochester Gas 8 <<ElectriC, Corp,,

'RE<<CIPi NAME<

RECIPIENT AFFILIATION ORUTCHFIELDiD~

Operating Reactors Br anch

,"5

SUBJECT:

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$0$lK ROCHESTER GAS AND ELECTRIC CORI7ORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vie PreetIent 7 C I.CP H0 N C 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. Crutchfield:

8 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 fulfillthe 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

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ROCHESTER GAS ANP ELECTRIC CORP.

pATE November 29, 1983 To Mr. Dennis M. Crutchfield SHEET NO.

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

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ROCHESTER GAS AND ELECTRIC CORP.

DATE November 29, l983 To Mr. Dennis M. Crutchfield SHEET NO.

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

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