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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 8, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 8, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating  
: Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295  


==SUBJECT:==
==SUBJECT:==
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE V-9 (TAC NOS. MF6238 AND MF6239)  
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE V-9 (TAC NOS. MF6238 AND MF6239)  


==Dear Mr. Pierce:==
==Dear Mr. Pierce:==
By letter dated May 4, 2015, Southern Nuclear Operating Company, Inc. requested Nuclear Regulatory Commission (NRC) authorization of alternative V-9 for the HNP for the fifth Ten-Year Interval lnservice Testing Program. In order to continue the review, the NRC staff requests additional information as discussed in the Enclosure. It is requested that your response be provided within thirty (30) days of the date of this letter. Docket Nos. 50-321 and 50-366  
By letter dated May 4, 2015, Southern Nuclear Operating  
: Company, Inc. requested Nuclear Regulatory Commission (NRC) authorization of alternative V-9 for the HNP for the fifth Ten-Year Interval lnservice Testing Program.
In order to continue the review, the NRC staff requests additional information as discussed in the Enclosure.
It is requested that your response be provided within thirty (30) days of the date of this letter. Docket Nos. 50-321 and 50-366
 
==Enclosure:==
 
Request for Additional Information cc: Distribution via Listserv Sincerely,
) J:l _l------1. tl.N'C/\.*J ob artin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE V-9 FOR THE INSERVICE TESTING PROGRAM FIFTH 10-YEAR INTERVAL EDWIN I. HATCH PLANT UNITS 1 & 2 (HNP) By letter dated May 4, 2015, Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15124A904, the Southern Nuclear Operating
: Company, Inc. (the licensee) requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(2),
for alternative testing associated with the inservice testing (IST) program fifth 10-year interval for the HNP. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following question:
1 O CFR Section 50.55a(f)(4),
"lnservice testing standards requ.irement for operating plants,"
: requires, in part, that IST of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components must meet the requirements of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). 10 CFR 50.55a(z) provides that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used when authorized by NRC. In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (1 O CFR 50.55a(z)(1
)) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).
Proposed alternative V-9 requests an alternative for testing excess flow check valves (EFCV). The alternative is to test EFCVs at a frequency specified in Technical Specifications (TS) Surveillance Requirement (SR) 3.6.1.3.8.
TS SR 3.6.1.3.8 allows a "representative sample" of EFCVs to be tested every refueling outage, such that each EFCV will be individually tested approximately every 1 O years. Justification for the relief request is based on General Electric (GE) Topical Report NED0-32977-A "Excess Flow Check Valve Testing Relaxation" dated . June 2000. The topical report provided:
(1) an estimate of steam release frequency (into the reactor building) due to a break in an instrument line concurrent with an EFCV failure to close, (2) and assessment of the radiological consequences of such a release.
The NRC staff reviewed the GE topical report and issued its evaluation on March 14, 2000 (ADAMS Accession No. ML003691722).
In its evaluation, the NRC staff found that the test interval could be extended up to a maximum of 10 years. In conjunction with this finding, the NRC staff noted that each licensee that adopts the relaxed test interval program for EFCVs must have a failure feedback mechanism and corrective action program (CAP) to ensure EFCV performance continues to be bounded by the topical report results.
Enclosure  Please explain HNP failure feedback mechanism and CAP. Also, please explain how the CAP will evaluate component failures and establish appropriate corrective actions.
Mr. C. R. Pierce Regulatory Affairs Director September 8, 2015 Southern Nuclear Operating
: Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295
 
==SUBJECT:==
 
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON V-9 (TAC NOS. MF6238 AND MF6239)
 
==Dear Mr. Pierce:==
By letter dated May 4, 2015, Southern Nuclear Operating
: Company, Inc. requested Nuclear Regulatory Commission (NRC) authorization of alternative V-9 for the HNP for the fifth Ten-Year Interval lnservice Testing Program.
In order to continue the review, the NRC staff requests additional informatioh as discussed in the Enclosure.
It is requested that your response be ' provided within thirty (30) days of the date of this letter. Docket. Nos. 50-321 and 50-366  


==Enclosure:==
==Enclosure:==
Request for Additional Information cc: Distribution via Listserv Sincerely, ) J:l _l------1. tl.N'C/\.*J ob artin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE V-9 FOR THE INSERVICE TESTING PROGRAM FIFTH 10-YEAR INTERVAL EDWIN I. HATCH PLANT UNITS 1 & 2 (HNP) By letter dated May 4, 2015, Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15124A904, the Southern Nuclear Operating Company, Inc. (the licensee) requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(2), for alternative testing associated with the inservice testing (IST) program fifth 10-year interval for the HNP. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following question: 1 O CFR Section 50.55a(f)(4), "lnservice testing standards requ.irement for operating plants," requires, in part, that IST of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components must meet the requirements of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). 10 CFR 50.55a(z) provides that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used when authorized by NRC. In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (1 O CFR 50.55a(z)(1 )) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)). Proposed alternative V-9 requests an alternative for testing excess flow check valves (EFCV). The alternative is to test EFCVs at a frequency specified in Technical Specifications (TS) Surveillance Requirement (SR) 3.6.1.3.8. TS SR 3.6.1.3.8 allows a "representative sample" of EFCVs to be tested every refueling outage, such that each EFCV will be individually tested approximately every 1 O years. Justification for the relief request is based on General Electric (GE) Topical Report NED0-32977-A "Excess Flow Check Valve Testing Relaxation" dated . June 2000. The topical report provided: (1) an estimate of steam release frequency (into the reactor building) due to a break in an instrument line concurrent with an EFCV failure to close, (2) and assessment of the radiological consequences of such a release. The NRC staff reviewed the GE topical report and issued its evaluation on March 14, 2000 (ADAMS Accession No. ML003691722). In its evaluation, the NRC staff found that the test interval could be extended up to a maximum of 10 years. In conjunction with this finding, the NRC staff noted that each licensee that adopts the relaxed test interval program for EFCVs must have a failure feedback mechanism and corrective action program (CAP) to ensure EFCV performance continues to be bounded by the topical report results. Enclosure  Please explain HNP failure feedback mechanism and CAP. Also, please explain how the CAP will evaluate component failures and establish appropriate corrective actions. 


ML15240A259 Sincerely, /RA/ Bob Martin, Senior Project Manager Plantlicensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Request for Additional Information cc: Distribution via Listserv DISTRIBUTION:
* RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource GBedi, NRR OFFICE DORULPL2-1/PM DORULPL2-1 /LA DSS/STSB/BC DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME RMartin SFigueroa DAiiey RPascarelli RMartin DATE 09/08/15 09/01/15 08/26/15 09/08/15 09/08/15}}
PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrLASFigueroa Resource RidsNrrPMHatch Resource ADAMS Accession No.: ML15240A259 Sincerely,  
/RA/ Bob Martin, Senior Project Manager Plantlicensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
* RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource GBedi, NRR OFFICE DORULPL2-1/PM DORULPL2-1  
/LA DSS/STSB/BC DORL/LPL2-1  
/BC DORL/LPL2-1  
/PM NAME RMartin SFigueroa DAiiey RPascarelli RMartin DATE 09/08/15 09/01/15 08/26/15 09/08/15 09/08/15 OFFICIAL RECORD COPY}}

Revision as of 20:45, 30 June 2018

Edwin I. Hatch Nuclear Plant - Units 1 and 2 (HNP) - Request for Additional Information on Alternative V-9 (TAC Nos. MF6238 and MF6239)
ML15240A259
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 09/08/2015
From: Martin R E
Plant Licensing Branch II
To: Pierce C R
Southern Nuclear Operating Co
Martin R E
References
TAC MF6238, TAC MF6239
Download: ML15240A259 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 8, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating

Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE V-9 (TAC NOS. MF6238 AND MF6239)

Dear Mr. Pierce:

By letter dated May 4, 2015, Southern Nuclear Operating

Company, Inc. requested Nuclear Regulatory Commission (NRC) authorization of alternative V-9 for the HNP for the fifth Ten-Year Interval lnservice Testing Program.

In order to continue the review, the NRC staff requests additional information as discussed in the Enclosure.

It is requested that your response be provided within thirty (30) days of the date of this letter. Docket Nos. 50-321 and 50-366

Enclosure:

Request for Additional Information cc: Distribution via Listserv Sincerely,

) J:l _l------1. tl.N'C/\.*J ob artin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE V-9 FOR THE INSERVICE TESTING PROGRAM FIFTH 10-YEAR INTERVAL EDWIN I. HATCH PLANT UNITS 1 & 2 (HNP) By letter dated May 4, 2015, Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15124A904, the Southern Nuclear Operating

Company, Inc. (the licensee) requested authorization, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(2),

for alternative testing associated with the inservice testing (IST) program fifth 10-year interval for the HNP. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following question:

1 O CFR Section 50.55a(f)(4),

"lnservice testing standards requ.irement for operating plants,"

requires, in part, that IST of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components must meet the requirements of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). 10 CFR 50.55a(z) provides that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used when authorized by NRC. In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (1 O CFR 50.55a(z)(1

)) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).

Proposed alternative V-9 requests an alternative for testing excess flow check valves (EFCV). The alternative is to test EFCVs at a frequency specified in Technical Specifications (TS) Surveillance Requirement (SR) 3.6.1.3.8.

TS SR 3.6.1.3.8 allows a "representative sample" of EFCVs to be tested every refueling outage, such that each EFCV will be individually tested approximately every 1 O years. Justification for the relief request is based on General Electric (GE) Topical Report NED0-32977-A "Excess Flow Check Valve Testing Relaxation" dated . June 2000. The topical report provided:

(1) an estimate of steam release frequency (into the reactor building) due to a break in an instrument line concurrent with an EFCV failure to close, (2) and assessment of the radiological consequences of such a release.

The NRC staff reviewed the GE topical report and issued its evaluation on March 14, 2000 (ADAMS Accession No. ML003691722).

In its evaluation, the NRC staff found that the test interval could be extended up to a maximum of 10 years. In conjunction with this finding, the NRC staff noted that each licensee that adopts the relaxed test interval program for EFCVs must have a failure feedback mechanism and corrective action program (CAP) to ensure EFCV performance continues to be bounded by the topical report results.

Enclosure Please explain HNP failure feedback mechanism and CAP. Also, please explain how the CAP will evaluate component failures and establish appropriate corrective actions.

Mr. C. R. Pierce Regulatory Affairs Director September 8, 2015 Southern Nuclear Operating

Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON V-9 (TAC NOS. MF6238 AND MF6239)

Dear Mr. Pierce:

By letter dated May 4, 2015, Southern Nuclear Operating

Company, Inc. requested Nuclear Regulatory Commission (NRC) authorization of alternative V-9 for the HNP for the fifth Ten-Year Interval lnservice Testing Program.

In order to continue the review, the NRC staff requests additional informatioh as discussed in the Enclosure.

It is requested that your response be ' provided within thirty (30) days of the date of this letter. Docket. Nos. 50-321 and 50-366

Enclosure:

Request for Additional Information cc: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrLASFigueroa Resource RidsNrrPMHatch Resource ADAMS Accession No.: ML15240A259 Sincerely,

/RA/ Bob Martin, Senior Project Manager Plantlicensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

  • RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource GBedi, NRR OFFICE DORULPL2-1/PM DORULPL2-1

/LA DSS/STSB/BC DORL/LPL2-1

/BC DORL/LPL2-1

/PM NAME RMartin SFigueroa DAiiey RPascarelli RMartin DATE 09/08/15 09/01/15 08/26/15 09/08/15 09/08/15 OFFICIAL RECORD COPY

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