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=Text=
=Text=
{{#Wiki_filter:REQUL'AiTORlf'NFORMAA"LOVEDDISTR'IBUTlON> SYSTEMI (RXD8)
{{#Wiki_filter:REQUL'AiTORlf'NFORMAA"LOVEDDISTR'IBUTlON> SYSTEMI (RXD8)
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MA IER                                                                  TCLCDNONC VICC PRESIDENT                                                         ARCA CODC Tla 546-2700 November 6, 1981             /If
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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
////I//I/I 8P.'::,
ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E.
MAIER VICC PRESIDENT TCLCDNONC ARCA CODC Tla 546-2700 November 6,
1981 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
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==Subject:==
==Subject:==
Environmental Qualification of Electrical Equipment R. E. Ginna Nuclear Power Plant Docket No. 50-244
Environmental Qualification of Electrical Equipment R. E. Ginna Nuclear Power Plant Docket No. 50-244


==Dear Mr.                 Crutchfield:==
==Dear Mr. Crutchfield:==
 
Rochester Gas and Electric submitted environmental qualifi-cation information relative to installed "TMI items" by {{letter dated|date=January 30, 1981|text=letter dated January 30, 1981}}.
Rochester             Gas and Electric submitted environmental qualifi-cation information relative to installed                       "TMI items" by letter dated January 30, 1981. Recently, the NRC consultants, Franklin Research Center, requested that we resubmit this information, as well         as provide the status of several other NUREG-0737 items.
: Recently, the NRC consultants, Franklin Research
This information is enclosed. The qualification documentation is being provided only to Mr. Cyril Crane of FRC.
: Center, requested that we resubmit this information, as well as provide the status of several other NUREG-0737 items.
RG&E also takes this opportunity to note that a failure evaluation of the DB-50 breakers (used for reactor trip) under adverse conditions such as high temperature, high humidity, flooding, and vibration is provided in Section 3.5 of WCAP-7706-L, "An Evaluation of Solid State Logic Reactor Protection in Anticipated Transients" by W. C. Gangloff and W. D. Loftus, dated July 1971. Although qualitative in nature, this report does provide additional indication that. the reactor trip breakers would perform their function (fail-safe) in the short. time they are required. This WCAP is in the possession of the NRC, and should be provided to FRC. This explanation should resolve item
This information is enclosed.
    -28b of RG&E's September 4, 1981 "90-day-response" to the NRC/FRC Environmental Qualification Evaluation for Ginna.
The qualification documentation is being provided only to Mr. Cyril Crane of FRC.
RG&E also takes this opportunity to note that a failure evaluation of the DB-50 breakers (used for reactor trip) under adverse conditions such as high temperature, high humidity,
: flooding, and vibration is provided in Section 3.5 of WCAP-7706-L, "An Evaluation of Solid State Logic Reactor Protection in Anticipated Transients" by W.
C. Gangloff and W. D. Loftus, dated July 1971.
Although qualitative in nature, this report does provide additional indication that. the reactor trip breakers would perform their function (fail-safe) in the short. time they are required.
This WCAP is in the possession of the NRC, and should be provided to FRC.
This explanation should resolve item
-28b of RG&E's September 4,
1981 "90-day-response" to the NRC/FRC Environmental Qualification Evaluation for Ginna.
Very truly yours,
Very truly yours,
  ,'DR p
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            <DOCK OSOOOpyy         aiii06                      E. Maier PDR Enclosure xc:         Cyril             Crane, FRC
<DOCK OSOOOpyy PDR Enclosure xc:
                                                                                            ~l   II
Cyril Crane, FRC E. Maier
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Enclosure to Letter from John E. Maier to Dennis M. Crutchfield, "Environmental Qualification of Electrical Equipment,"
Enclosure to Letter from John E. Maier to Dennis M. Crutchfield, "Environmental Qualification of Electrical Equipment,"
November 6, 1981 NUREG-0737 Item Status
November 6,
: 1. II.B.1 Head Vent Sytem - The solenoid valves controlling the head vent system are fully qualified for post-accident, operation inside containment. .This qualification report entitled "Qualification Test. Report for IEEE Class IE Solenoid Valves", QR 52600-5940-.2 is .being submitted to the NRC consultants, Franklin Research Center. This should be designated Reference 2.73.       It should be noted that this system is 'required to be installed by July 1, 1982 under the NUREG-0737 schedule.
1981 NUREG-0737 Item Status 1.
: 2. II-B.3 Post-accident sampling The post-accident sampling system is not yet installed at Ginna. The scheduled imple-mentation date is July 1, 1982. No documentation is thus required at this time.
II.B.1 Head Vent Sytem - The solenoid valves controlling the head vent system are fully qualified for post-accident, operation inside containment.
: 3. II-D.3 Direct Indication of Valve Position - Position indication for the pressurizer safety and relief valves is provided via LVDT s and NAMCO limit switches, respectively, as stated in RG&E's letter of January 30, 1981 from John E. Maier to Darrell G. Eisenhut of the NRC. These items are located in a harsh environment (the containment).
.This qualification report entitled "Qualification Test. Report for IEEE Class IE Solenoid Valves",
The following qualification documentation is being provided directly to the NRC consultants, Franklin Research Center, together with a copy of this submittal:
QR 52600-5940-.2 is.being submitted to the NRC consultants, Franklin Research Center.
(1) Reference 2.74: Environment, Qualification Report, on Pressurizer Safety Valve Position Indication System,
This should be designated Reference 2.73.
        'inna   Station, Direct Indication of Valve Position (2) Reference 2.75: NAMCO Test Report, April 3, 1980
It should be noted that this system is 'required to be installed by July 1, 1982 under the NUREG-0737 schedule.
: 4. II.E.1.2 Auxiliary feedwater initiation and flow - The auxiliary feedwater initiation system at Ginna has always been safety-grade. No modifications to the system were required as the result of NUREG-0737. The auxiliary feed-water system is initiated by a Safety Injection signal, as well as low steam generator water level, loss of 4 Kv bus voltage, and feedwater pump breakers "open". These latter two signals are initiated by instrumentation in the turbine building, which is a "mild environment" under transient conditions for which this instrumentation is installed. The instrumentation generating a Safety Injection signal, as well as steam generator level, was discussed in RGSE's previous submittals, and no additional information is re-quired. RGSE has previously committed to replace those transmitters located in a harsh environment (see RG&E's October 31, 1980 and September 4, 1981 letters for the latest commitment status for this equipment).
2.
II-B.3 Post-accident sampling The post-accident sampling system is not yet installed at Ginna.
The scheduled imple-mentation date is July 1, 1982.
No documentation is thus required at this time.
3.
II-D.3 Direct Indication of Valve Position - Position indication for the pressurizer safety and relief valves is provided via LVDT s and NAMCO limit switches, respectively, as stated in RG&E's letter of January 30, 1981 from John E. Maier to Darrell G. Eisenhut of the NRC.
These items are located in a harsh environment (the containment).
The following qualification documentation is being provided directly to the NRC consultants, Franklin Research
: Center, together with a copy of this submittal:
(1) Reference 2.74:
Environment, Qualification Report, on Pressurizer Safety Valve Position Indication System,
'inna Station, Direct Indication of Valve Position (2) Reference 2.75:
NAMCO Test Report, April 3, 1980 4.
II.E.1.2 Auxiliary feedwater initiation and flow - The auxiliary feedwater initiation system at Ginna has always been safety-grade.
No modifications to the system were required as the result of NUREG-0737.
The auxiliary feed-water system is initiated by a Safety Injection signal, as well as low steam generator water level, loss of 4 Kv bus
: voltage, and feedwater pump breakers "open".
These latter two signals are initiated by instrumentation in the turbine building, which is a "mild environment" under transient conditions for which this instrumentation is installed.
The instrumentation generating a Safety Injection signal, as well as steam generator level, was discussed in RGSE's previous submittals, and no additional information is re-quired.
RGSE has previously committed to replace those transmitters located in a harsh environment (see RG&E's October 31, 1980 and September 4,
1981 letters for the latest commitment status for this equipment).


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Auxiliary feedwater flow indication is provided by the Foxboro NE-10 series transmitters, which are located in the Intermediate Building in the vicinity of the auxiliary feedwater pumps. These transmitters are the same as those which RG&E has committed to install to replace the trans-mitters requiring environmental qualification, as noted in our October 31, 1980 submittal. These transmitters are still undergoing final qualification testing.
Auxiliary feedwater flow indication is provided by the Foxboro NE-10 series transmitters, which are located in the Intermediate Building in the vicinity of the auxiliary feedwater pumps.
It should be noted that, as stated in RG&E's October 31, 1980 submittal, the Standby Auxiliary Feedwater System, located in a mild environment, is sufficient to provide all required auxiliary feedwater system safety functions. Environmental qualification of auxilary feedwater system components is desirable, but not necessary.
These transmitters are the same as those which RG&E has committed to install to replace the trans-mitters requiring environmental qualification, as noted in our October 31, 1980 submittal.
II.E.3.1   Emergency Power for Pressurizer heaters - This TMI requirement, focuses on the availability of emergency power to pressurizer heaters. This is accomplished at the emergency electrical buses, which are located in the auxiliary building, a mild environment. No harsh environment qualification documentation is required to be provided.
These transmitters are still undergoing final qualification testing.
II.E.4.1 Dedicated hydrogen penetrations This requirement is not applicable to Ginna, since Ginna has redundant hydrogen recombiners inside containment.
It should be noted that, as stated in RG&E's October 31, 1980 submittal, the Standby Auxiliary Feedwater
II.E.4.2 Containment Isolation dependability This TMI requirement focuses only on equipment installed in the control and relay rooms at, Ginna. Since these. areas are subject only to a "mild" environment, no harsh environment qualification documentation is required to be submitted.
: System, located in a mild environment, is sufficient to provide all required auxiliary feedwater system safety functions.
II.F.2 Detection of Inadequate Core Cooling - As noted in RGB's January 30, 1981 letter, this is provided by a combi-nation of hot leg RTD's and reactor coolant, pressure instru-mentation. RGB's October 31, 1980 letter provided our plans for the qualification of this instrumentation.
Environmental qualification of auxilary feedwater system components is desirable, but not necessary.
II.G.1 Emergency Power to Pressurizer Equipment - This TMI requirement focuses on the availability of emergency power to pressurizer equipment. This is accomplished at the emergency electrical buses, which are located in the auxiliary building operating and intermediate floors (elevations 271 and 253). These areas are subject only to a "mild" environment. No documentation regarding qualification to a harsh environment, is thus required.
II.E.3.1 Emergency Power for Pressurizer heaters - This TMI requirement, focuses on the availability of emergency power to pressurizer heaters.
II.K.3.9 PID Controller - As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room). No documentation regarding qualification to a harsh environment is thus required.
This is accomplished at the emergency electrical buses, which are located in the auxiliary building, a mild environment.
No harsh environment qualification documentation is required to be provided.
II.E.4.1 Dedicated hydrogen penetrations This requirement is not applicable to Ginna, since Ginna has redundant hydrogen recombiners inside containment.
II.E.4.2 Containment Isolation dependability This TMI requirement focuses only on equipment installed in the control and relay rooms at, Ginna.
Since these. areas are subject only to a "mild" environment, no harsh environment qualification documentation is required to be submitted.
II.F.2 Detection of Inadequate Core Cooling - As noted in RGB's {{letter dated|date=January 30, 1981|text=January 30, 1981 letter}}, this is provided by a combi-nation of hot leg RTD's and reactor coolant, pressure instru-mentation.
RGB's {{letter dated|date=October 31, 1980|text=October 31, 1980 letter}} provided our plans for the qualification of this instrumentation.
II.G.1 Emergency Power to Pressurizer Equipment - This TMI requirement focuses on the availability of emergency power to pressurizer equipment.
This is accomplished at the emergency electrical buses, which are located in the auxiliary building operating and intermediate floors (elevations 271 and 253).
These areas are subject only to a "mild" environment.
No documentation regarding qualification to a harsh environment, is thus required.
II.K.3.9 PID Controller - As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room).
No documentation regarding qualification to a harsh environment is thus required.


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: 11. II.K.3.12 Anticipatory"turbine trip or reactor trip As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room). No documentation regarding qualification to a harsh environment is thus required.
 
11.
II.K.3.12 Anticipatory"turbine trip or reactor trip As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room).
No documentation regarding qualification to a harsh environment is thus required.


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Latest revision as of 10:52, 8 January 2025

Forwards Status of NUREG-0737 Items Re Environ Qualification of Electrical Equipment.Evaluation of DB-50 Breaker Failure Provided in WCAP-7706-L Indicates That Reactor Trip Breakers Would Function as Required
ML17258A306
Person / Time
Site: Ginna 
Issue date: 11/06/1981
From: Maier J
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.D.3, TASK-2.E.1.2, TASK-2.E.3.1, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.2, TASK-2.G.1, TASK-2.K.3.09, TASK-2.K.3.12, TASK-TM NUDOCS 8111130471
Download: ML17258A306 (9)
v • d • e


Text

REQUL'AiTORlf'NFORMAA"LOVEDDISTR'IBUTlON> SYSTEMI (RXD8)

ACCESSIONI NBR':8111 130471<

DOC',DATER'l/lf/96'OTARIZEDI-NO DOCKEITI ¹i FAGIIL460~2'04 Rbbel't< Ktnrnp'tc Ginnac Nucl e8rI Pl antg, Uhl t>>

1 g. Rochhstei i G 05090244 AUTHI,NAMEI A U THOR' F FIL'IAITCON M'A'IER~R Jt, Ef,:

Roch'ester.

Gas 8 Eile'ctr8c Corp~

RECLP~NAMEI RECiIPZENTL AFFILKAR'IONI CRUTCHFIELO~RD~,:

Gael atjng, Rb'actor s

Bhanch, Si SUBVECIl":KForwar dss status of NUREGr 073i7 i temp~ reI envir oni,.quaIl ificattionK of eel ectri eel equipment,EVal uatrlon~ of DB. SO, br esker T fag lureI prt)v'idetIt ini HcAP~?706'~LI indicates'hatt r eactori trip: bi'abkersi wou:ld functions as required.:

DKSTRKBUTKONi CODKII'OSSS:

CDPZEB'ECKKVED:L0'Ri

$'NCL( g'IZES: '

'IIITLEI:-

Eguipmpnt~ Qualification (OR'8 PRKI Ol;0 NOTES:1-copy:SEP'e'ctg,'.

LtIr's-05090284 RECXPIENTI IOl CODKi/NAMKI ACTitION;:

ORBI ¹Si BCI 12.

INTERNALc: ELOl 20, ARRI/DEI/EQBI 01, OGCI 2fK 6I CLC AMB< M'. H~. 9'6<

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6A 6v RECIIPX ENTI ID> CODEi/NAMEI SNAIIDER~e Ri, 0'1 K 14 I 8 El 18 5

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ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E.

MAIER VICC PRESIDENT TCLCDNONC ARCA CODC Tla 546-2700 November 6,

1981 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

/If

"'~~

~eel~:

Subject:

Environmental Qualification of Electrical Equipment R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

Rochester Gas and Electric submitted environmental qualifi-cation information relative to installed "TMI items" by letter dated January 30, 1981.

Recently, the NRC consultants, Franklin Research
Center, requested that we resubmit this information, as well as provide the status of several other NUREG-0737 items.

This information is enclosed.

The qualification documentation is being provided only to Mr. Cyril Crane of FRC.

RG&E also takes this opportunity to note that a failure evaluation of the DB-50 breakers (used for reactor trip) under adverse conditions such as high temperature, high humidity,

flooding, and vibration is provided in Section 3.5 of WCAP-7706-L, "An Evaluation of Solid State Logic Reactor Protection in Anticipated Transients" by W.

C. Gangloff and W. D. Loftus, dated July 1971.

Although qualitative in nature, this report does provide additional indication that. the reactor trip breakers would perform their function (fail-safe) in the short. time they are required.

This WCAP is in the possession of the NRC, and should be provided to FRC.

This explanation should resolve item

-28b of RG&E's September 4,

1981 "90-day-response" to the NRC/FRC Environmental Qualification Evaluation for Ginna.

Very truly yours,

,'DR

~> aiii06 p

<DOCK OSOOOpyy PDR Enclosure xc:

Cyril Crane, FRC E. Maier

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Enclosure to Letter from John E. Maier to Dennis M. Crutchfield, "Environmental Qualification of Electrical Equipment,"

November 6,

1981 NUREG-0737 Item Status 1.

II.B.1 Head Vent Sytem - The solenoid valves controlling the head vent system are fully qualified for post-accident, operation inside containment.

.This qualification report entitled "Qualification Test. Report for IEEE Class IE Solenoid Valves",

QR 52600-5940-.2 is.being submitted to the NRC consultants, Franklin Research Center.

This should be designated Reference 2.73.

It should be noted that this system is 'required to be installed by July 1, 1982 under the NUREG-0737 schedule.

2.

II-B.3 Post-accident sampling The post-accident sampling system is not yet installed at Ginna.

The scheduled imple-mentation date is July 1, 1982.

No documentation is thus required at this time.

3.

II-D.3 Direct Indication of Valve Position - Position indication for the pressurizer safety and relief valves is provided via LVDT s and NAMCO limit switches, respectively, as stated in RG&E's letter of January 30, 1981 from John E. Maier to Darrell G. Eisenhut of the NRC.

These items are located in a harsh environment (the containment).

The following qualification documentation is being provided directly to the NRC consultants, Franklin Research

Center, together with a copy of this submittal:

(1) Reference 2.74:

Environment, Qualification Report, on Pressurizer Safety Valve Position Indication System,

'inna Station, Direct Indication of Valve Position (2) Reference 2.75:

NAMCO Test Report, April 3, 1980 4.

II.E.1.2 Auxiliary feedwater initiation and flow - The auxiliary feedwater initiation system at Ginna has always been safety-grade.

No modifications to the system were required as the result of NUREG-0737.

The auxiliary feed-water system is initiated by a Safety Injection signal, as well as low steam generator water level, loss of 4 Kv bus

voltage, and feedwater pump breakers "open".

These latter two signals are initiated by instrumentation in the turbine building, which is a "mild environment" under transient conditions for which this instrumentation is installed.

The instrumentation generating a Safety Injection signal, as well as steam generator level, was discussed in RGSE's previous submittals, and no additional information is re-quired.

RGSE has previously committed to replace those transmitters located in a harsh environment (see RG&E's October 31, 1980 and September 4,

1981 letters for the latest commitment status for this equipment).

P-W I

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Auxiliary feedwater flow indication is provided by the Foxboro NE-10 series transmitters, which are located in the Intermediate Building in the vicinity of the auxiliary feedwater pumps.

These transmitters are the same as those which RG&E has committed to install to replace the trans-mitters requiring environmental qualification, as noted in our October 31, 1980 submittal.

These transmitters are still undergoing final qualification testing.

It should be noted that, as stated in RG&E's October 31, 1980 submittal, the Standby Auxiliary Feedwater

System, located in a mild environment, is sufficient to provide all required auxiliary feedwater system safety functions.

Environmental qualification of auxilary feedwater system components is desirable, but not necessary.

II.E.3.1 Emergency Power for Pressurizer heaters - This TMI requirement, focuses on the availability of emergency power to pressurizer heaters.

This is accomplished at the emergency electrical buses, which are located in the auxiliary building, a mild environment.

No harsh environment qualification documentation is required to be provided.

II.E.4.1 Dedicated hydrogen penetrations This requirement is not applicable to Ginna, since Ginna has redundant hydrogen recombiners inside containment.

II.E.4.2 Containment Isolation dependability This TMI requirement focuses only on equipment installed in the control and relay rooms at, Ginna.

Since these. areas are subject only to a "mild" environment, no harsh environment qualification documentation is required to be submitted.

II.F.2 Detection of Inadequate Core Cooling - As noted in RGB's January 30, 1981 letter, this is provided by a combi-nation of hot leg RTD's and reactor coolant, pressure instru-mentation.

RGB's October 31, 1980 letter provided our plans for the qualification of this instrumentation.

II.G.1 Emergency Power to Pressurizer Equipment - This TMI requirement focuses on the availability of emergency power to pressurizer equipment.

This is accomplished at the emergency electrical buses, which are located in the auxiliary building operating and intermediate floors (elevations 271 and 253).

These areas are subject only to a "mild" environment.

No documentation regarding qualification to a harsh environment, is thus required.

II.K.3.9 PID Controller - As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room).

No documentation regarding qualification to a harsh environment is thus required.

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11.

II.K.3.12 Anticipatory"turbine trip or reactor trip As noted in 9 above, this TMI review focuses only on equipment located in a "mild" environment (the relay room).

No documentation regarding qualification to a harsh environment is thus required.

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