ML17264B082: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 13: Line 13:
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 5
| page count = 5
| project =
| stage = Other
}}
}}
See also: [[see also::IR 05000244/1997201]]


=Text=
=Text=
{{#Wiki_filter:CATEGORY 1 REGULATORY
{{#Wiki_filter:CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM           (RIDS)
INFORMATION
ACCESSION NBR:9711120009           DOC.DATE: 97/11/03       NOTARIZED: NO             DOCKET FACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                   G   05000244 AUTH. NAME           AUTHOR AFFILIATION
DISTRIBUTION
  'MECREpY,R.C.         Rochester Gas a Electric Corp.
SYSTEM (RIDS)ACCESSION NBR:9711120009
RECIP.NAME           RECIPIENT AFFILIATION VISSING,.G.S.
DOC.DATE: 97/11/03 NOTARIZED:
 
NO DOCKET FACZL:50-244
==SUBJECT:==
Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION
Clarifies testing commitment made re insp rept 50-244/97-201
'MECREpY,R.C.
              & notifies that appropriate         alternative to clarified testing commitment has been performed during           current refueling                       C outa g e.
Rochester Gas a Electric Corp.RECIP.NAME
DISTRIBUTION,CODE: IE01D         COPIES RECEIVED:LTR         ENCL       SIZE:
RECIPIENT AFFILIATION
TITLE: General (50 Dkt)-Znsp Rept/Notice of             Violation   Response NOTES:License Exp date       in accordance with 10CFR2,2.109(9/19/72).                 05000244     E G,
VISSING,.G.S.
RECIPIENT            COPIES              RECIPIENT           COPIES ID CODE/NAME          LTTR ENCL          ID CODE/NAME         LTTR ENCL PD1-1 PD                               VISSING,G.
SUBJECT: Clarifies testing commitment
INTERNAL: AEOD/SPD/RAB                 1            AEOD
made re insp rept 50-244/97-201
            .DEDRO                   '1              LE CENTE NRR/DISP/PIPB             1                    CH/HHFB NRR/DRPM/PECB             1            NRR/DRPM/PERB NUDOCS-ABSTRACT           1            OE DIR OGC/HDS3                 1            RGN1    FILE  01 XTERNAL: LZTCO BRYCE,J H                           NOAC NRC PDR                                 NUDOCS FULLTEXT                                   D 0
&notifies that appropriate
N NOTE TO ALL "RIDS" RECIPIENTS:
alternative
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR             18   ENCL
to clarified testing commitment
 
has been performed during current refueling outa e.g DISTRIBUTION,CODE:
0 November 3, 1997 U.S. Nuclear Regulatory Commission Document   Control Desk Attn:       Guy S. Vissing Directorate I-1
IE01D COPIES RECEIVED:LTR
                            'roject Washington, D.C. 20555
ENCL SIZE: TITLE: General (50 Dkt)-Znsp Rept/Notice
 
of Violation Response C NOTES:License
==Subject:==
Exp date in accordance
Clarification of       A/E Inspection Commitment NRC Inspection Report       No. 50-244/97-201 R. E. Ginna Nuclear Power Plant Docket No. 50-244
with 10CFR2,2.109(9/19/72).
 
05000244 E G, RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB.DEDRO NRR/DISP/PIPB
==Dear Mr. Vissing:==
NRR/DRPM/PECB
 
NUDOCS-ABSTRACT
During the period from June         9 through August 15) 1997                 the U S.
OGC/HDS3 XTERNAL: LZTCO BRYCE,J H NRC PDR COPIES LTTR ENCL 1'1 1 1 1 1 RECIPIENT ID CODE/NAME VISSING,G.
Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR) performed an A/E Inspection of the R.E. Ginna Nuclear Power Plant. During this inspection, the NRC inferred that Rochester Gas & Electric (RG&E) had committed to performing seat leakage testing for two Component Cooling Water (CCW) System check valves. The intent of this correspondence is to clarify the testing commitment made by RG&E. Also, RG&E wishes to notify the NRC that an appropriate alternative to the clarified testing commitment has been performed during the current refueling outage.
AEOD LE CENTE CH/HHFB NRR/DRPM/PERB
Due to the short period of time from the receipt of NRC Inspection Report 50-244/97-201 to the projected completion of this refueling outage, RG&E believes         it is prudent to notify the NRC of the check valve test clarification and proposed alternative now, rather than 60 days after issuance of the inspection report. As requested in the inspection report, RG&E will provide a schedule for completion of corrective actions, where applicable, within 60 days of issuance of the inspection report.
OE DIR RGN1 FILE 01 NOAC NUDOCS FULLTEXT COPIES LTTR ENCL D 0 N NOTE TO ALL"RIDS" RECIPIENTS:
NRC Inspection Report No. 50-244/97-201, under Section El (Conduct of Engineering), Item E1. 2. 2. 2 (d) (CCW System Testing)                     l gg]
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION
states:
REMOVED FROM DISTRIBUTION
      "the licensee stated that valves 753A and B would be added to the in-service inspection program and require leak testing."
LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL  
It is correct that check valves 753A and 753B will be added to the Ginna Station Inservice Testing Program, but with a test requirement of check valve closure verification testing and not seat leakage testing.
0  
II!Ill!(llllll/llllllllllllillf Illa'll
November 3, 1997 U.S.Nuclear Regulatory
 
Commission
Check valves 753A and 753B are in the CCW System supply piping to the reactor coolant pump thermal barriers. Although these valves
Document Control Desk Attn: Guy S.Vissing'roject Directorate
'are designed as pressure class boundaries between the Reactor Coolant System and the lower pressure CCW System, they are not, considered pressure isolation valves (PIVs) since, should a thermal barrier leak occur, the associated CCW piping is protected from overpressure by pressure relief valves and the Ginna Station licensing basis considers a thermal barrier leak as a small break loss of coolant accident.
I-1 Washington, D.C.20555 Subject: Clarification
Since the capacity of the associated pressure relief valves is sufficient to provide overpressure protection for the affected CCW System piping should a thermal barrier leak occur, the safety function of check valves 753A and 753B is to close to mitigate the consequences of the accident. Thus, seat, leakage in the closed position is inconsequential.
of A/E Inspection
Therefore, RG&E agrees that 753A  and  753B to periodic it is prudent to subject check valves inservice testing to verify closure capability. In order to perform closure verification testing, a modification is required to install suitable test connections.
Commitment
Due to the short amount of time from when the commitment for inservice testing was made prior to the commencement of the current refueling outage, the proper preparations were not able to be made to perform this required modification. However, RG&E has disassembled check valves 753A and 753B during this refueling outage to verify valve obturator movement to the closed position in accordance with OMa-1988, Part 10, Section 4.3.2.4. This 2 of activity is an acceptable alternative pursuant to Position request NRC Generic Letter 89-04 and, as such, does not require a for relief from Code requirements.
NRC Inspection
RG&E intends to modify the affected piping system to install suitable test connections during the Spring, 1999 refueling outage and to commence the periodic closure verification testing schedule in accordance with the Ginna Station Inservice Testing Program at that time.
Report No.50-244/97-201
Very truly yours,
R.E.Ginna Nuclear Power Plant Docket No.50-244 Dear Mr.Vissing: During the period from June 9 through August 15)1997 the U S.Nuclear Regulatory
                                      /~grq '
Commission (NRC), Office of Nuclear Reactor Regulation (NRR)performed an A/E Inspection
Robert C. Mecredy GJW5482
of the R.E.Ginna Nuclear Power Plant.During this inspection, the NRC inferred that Rochester Gas&Electric (RG&E)had committed to performing
 
seat leakage testing for two Component Cooling Water (CCW)System check valves.The intent of this correspondence
xc: Mr. Guy S. Vissing (Mail Stop 14B2)
is to clarify the testing commitment
    .Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA   19406 US NRC Ginna Senior Resident Inspector}}
made by RG&E.Also, RG&E wishes to notify the NRC that an appropriate
alternative
to the clarified testing commitment
has been performed during the current refueling outage.Due to the short period of time from the receipt of NRC Inspection
Report 50-244/97-201
to the projected completion
of this refueling outage, RG&E believes it is prudent to notify the NRC of the check valve test clarification
and proposed alternative
now, rather than 60 days after issuance of the inspection
report.As requested in the inspection
report, RG&E will provide a schedule for completion
of corrective
actions, where applicable, within 60 days of issuance of the inspection
report.NRC Inspection
Report No.50-244/97-201, under Section El (Conduct of Engineering), Item E1.2.2.2 (d)(CCW System Testing)l gg]states: "the licensee stated that valves 753A and B would be added to the in-service
inspection
program and require leak testing." It is correct that check valves 753A and 753B will be added to the Ginna Station Inservice Testing Program, but with a test requirement
of check valve closure verification
testing and not seat leakage testing.II!Ill!(llllll/llllllllllllillf
Illa'll  
Check valves 753A and 753B are in the CCW System supply piping to the reactor coolant pump thermal barriers.Although these valves'are designed as pressure class boundaries
between the Reactor Coolant System and the lower pressure CCW System, they are not, considered
pressure isolation valves (PIVs)since, should a thermal barrier leak occur, the associated
CCW piping is protected from overpressure
by pressure relief valves and the Ginna Station licensing basis considers a thermal barrier leak as a small break loss of coolant accident.Since the capacity of the associated
pressure relief valves is sufficient
to provide overpressure
protection
for the affected CCW System piping should a thermal barrier leak occur, the safety function of check valves 753A and 753B is to close to mitigate the consequences
of the accident.Thus, seat, leakage in the closed position is inconsequential.
Therefore, RG&E agrees that it is prudent to subject check valves 753A and 753B to periodic inservice testing to verify closure capability.
In order to perform closure verification
testing, a modification
is required to install suitable test connections.
Due to the short amount of time from when the commitment
for inservice testing was made prior to the commencement
of the current refueling outage, the proper preparations
were not able to be made to perform this required modification.
However, RG&E has disassembled
check valves 753A and 753B during this refueling outage to verify valve obturator movement to the closed position in accordance
with OMa-1988, Part 10, Section 4.3.2.4.This activity is an acceptable
alternative
pursuant to Position 2 of NRC Generic Letter 89-04 and, as such, does not require a request for relief from Code requirements.
RG&E intends to modify the affected piping system to install suitable test connections
during the Spring, 1999 refueling outage and to commence the periodic closure verification
testing schedule in accordance
with the Ginna Station Inservice Testing Program at that time.Very truly yours,/~grq'Robert C.Mecredy GJW5482  
xc: Mr.Guy S.Vissing (Mail Stop 14B2).Project Directorate
I-1 Washington, D.C.20555 U.S.Nuclear Regulatory
Commission
Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
}}

Latest revision as of 04:19, 4 December 2019

Clarifies Testing Commitment Made Re Insp Rept 50-244/97-201 & Notifies That Appropriate Alternative to Clarified Testing Commitment Has Been Performed During Current Refueling Outage
ML17264B082
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/03/1997
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
50-244-97-201, GL-89-04, GL-89-4, NUDOCS 9711120009
Download: ML17264B082 (5)
v • d • e


Text

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9711120009 DOC.DATE: 97/11/03 NOTARIZED: NO DOCKET FACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION

'MECREpY,R.C. Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,.G.S.

SUBJECT:

Clarifies testing commitment made re insp rept 50-244/97-201

& notifies that appropriate alternative to clarified testing commitment has been performed during current refueling C outa g e.

DISTRIBUTION,CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: General (50 Dkt)-Znsp Rept/Notice of Violation Response NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E G,

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD VISSING,G.

INTERNAL: AEOD/SPD/RAB 1 AEOD

.DEDRO '1 LE CENTE NRR/DISP/PIPB 1 CH/HHFB NRR/DRPM/PECB 1 NRR/DRPM/PERB NUDOCS-ABSTRACT 1 OE DIR OGC/HDS3 1 RGN1 FILE 01 XTERNAL: LZTCO BRYCE,J H NOAC NRC PDR NUDOCS FULLTEXT D 0

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL

0 November 3, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Directorate I-1

'roject Washington, D.C. 20555

Subject:

Clarification of A/E Inspection Commitment NRC Inspection Report No. 50-244/97-201 R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

During the period from June 9 through August 15) 1997 the U S.

Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR) performed an A/E Inspection of the R.E. Ginna Nuclear Power Plant. During this inspection, the NRC inferred that Rochester Gas & Electric (RG&E) had committed to performing seat leakage testing for two Component Cooling Water (CCW) System check valves. The intent of this correspondence is to clarify the testing commitment made by RG&E. Also, RG&E wishes to notify the NRC that an appropriate alternative to the clarified testing commitment has been performed during the current refueling outage.

Due to the short period of time from the receipt of NRC Inspection Report 50-244/97-201 to the projected completion of this refueling outage, RG&E believes it is prudent to notify the NRC of the check valve test clarification and proposed alternative now, rather than 60 days after issuance of the inspection report. As requested in the inspection report, RG&E will provide a schedule for completion of corrective actions, where applicable, within 60 days of issuance of the inspection report.

NRC Inspection Report No. 50-244/97-201, under Section El (Conduct of Engineering), Item E1. 2. 2. 2 (d) (CCW System Testing) l gg]

states:

"the licensee stated that valves 753A and B would be added to the in-service inspection program and require leak testing."

It is correct that check valves 753A and 753B will be added to the Ginna Station Inservice Testing Program, but with a test requirement of check valve closure verification testing and not seat leakage testing.

II!Ill!(llllll/llllllllllllillf Illa'll

Check valves 753A and 753B are in the CCW System supply piping to the reactor coolant pump thermal barriers. Although these valves

'are designed as pressure class boundaries between the Reactor Coolant System and the lower pressure CCW System, they are not, considered pressure isolation valves (PIVs) since, should a thermal barrier leak occur, the associated CCW piping is protected from overpressure by pressure relief valves and the Ginna Station licensing basis considers a thermal barrier leak as a small break loss of coolant accident.

Since the capacity of the associated pressure relief valves is sufficient to provide overpressure protection for the affected CCW System piping should a thermal barrier leak occur, the safety function of check valves 753A and 753B is to close to mitigate the consequences of the accident. Thus, seat, leakage in the closed position is inconsequential.

Therefore, RG&E agrees that 753A and 753B to periodic it is prudent to subject check valves inservice testing to verify closure capability. In order to perform closure verification testing, a modification is required to install suitable test connections.

Due to the short amount of time from when the commitment for inservice testing was made prior to the commencement of the current refueling outage, the proper preparations were not able to be made to perform this required modification. However, RG&E has disassembled check valves 753A and 753B during this refueling outage to verify valve obturator movement to the closed position in accordance with OMa-1988, Part 10, Section 4.3.2.4. This 2 of activity is an acceptable alternative pursuant to Position request NRC Generic Letter 89-04 and, as such, does not require a for relief from Code requirements.

RG&E intends to modify the affected piping system to install suitable test connections during the Spring, 1999 refueling outage and to commence the periodic closure verification testing schedule in accordance with the Ginna Station Inservice Testing Program at that time.

Very truly yours,

/~grq '

Robert C. Mecredy GJW5482

xc: Mr. Guy S. Vissing (Mail Stop 14B2)

.Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector

Retrieved from "https://kanterella.com/w/index.php?title=ML17264B082&oldid=2228093"