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| issue date = 09/30/1997
| issue date = 09/30/1997
| title = NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
| title = NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
| author name = Roe J W
| author name = Roe J
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 7
| page count = 7
}}
}}
{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001September 30, 1997NRC ADMINISTRATIVE LETTER 97-04: NRC STAFF APPROVAL FOR CHANGES TO10 CFR PART 50, APPENDIX H, REACTORVESSEL SURVEILLANCE SPECIMENWITHDRAWAL SCHEDULES
{{#Wiki_filter:UNITED STATES
                            NUCLEAR REGULATORY COMMISSION
                        OFFICE OF NUCLEAR REACTOR REGULATION
                                WASHINGTON, D.C. 20555-0001 September 30, 1997 NRC ADMINISTRATIVE LETTER 97-04:               NRC STAFF APPROVAL FOR CHANGES TO
                                                10 CFR PART 50, APPENDIX H, REACTOR
                                                VESSEL SURVEILLANCE SPECIMEN
                                                WITHDRAWAL SCHEDULES


==Addressees==
==Addressees==
All holders of operating licenses for nuclear power reactors except those who havepermanently ceased operations and have certified that fuel has been permanently removedfrom the reactor vessel.
All holders of operating licenses for nuclear power reactors except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to informlicensees that changes to their facilities' reactor vessel surveillance specimen capsulewithdrawal schedules as specified in Appendix H to Part 50 of Title 10 of the Code of FederalRegulations (10 CFR) that do not conform to the required ASTM standard referenced inAppendix H will be treated as license amendments requiring public notice and opportunity fora hearing.BackgroundIn a Memorandum and Order (CLI-96-13) issued in the Perry operating license amendmentproceeding on December 6, 1996, the Commission reversed and vacated the Atomic Safetyand Licensing Board Order, LBP-95-17, which required that all future proposed withdrawalschedule changes be treated as license amendments. The Commission found that while10 CFR Part 50, Appendix H, II.B.3 requires prior NRC approval for all withdrawal schedulechanges, only certain changes require license amendments as the process to be followed forsuch approval. Specifically, those changes that do not conform to the ASTM standardreferenced in Appendix H (ASTM E-185, Standard Practice for Conducting Surveillance Testsfor Light-Water Cooled Nuclear Power Reactor Vessels) will require approval by the licenseamendment process, whereas changes that conform to the ASTM standard require only staffverification of such conformance.DiscussionPlant technical specifications often direct licensees to conduct testing and surveillance ofmaterial specimens according to Appendix H. Appendix H, in tum, requires withdrawalschedules to meet an applicable ASTM standard. In this instance, as long as the plant'swithdrawal schedule change meets the applicable ASTM standard, the plant will not be l~9~92?0 PK W UO q1011r -vW ,  
The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to inform licensees that changes to their facilities' reactor vessel surveillance specimen capsule withdrawal schedules as specified in Appendix H to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) that do not conform to the required ASTM standard referenced in Appendix H will be treated as license amendments requiring public notice and opportunity for a hearing.
AL 97-04September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a licenseamendment would not be required, although prior NRC approval to verify conformance withthe ASTM standard is required by Appendix H.However, if the plant's withdrawal schedule change does not meet the applicable ASTMstandard, then the change will be treated as a license amendment requiring public notice andopportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in suchsubmittals.
 
Background In a Memorandum and Order (CLI-96-13) issued in the Perry operating license amendment proceeding on December 6, 1996, the Commission reversed and vacated the Atomic Safety and Licensing Board Order, LBP-95-17, which required that all future proposed withdrawal schedule changes be treated as license amendments. The Commission found that while
10 CFR Part 50, Appendix H, II.B.3 requires prior NRC approval for all withdrawal schedule changes, only certain changes require license amendments as the process to be followed for such approval. Specifically, those changes that do not conform to the ASTM standard referenced in Appendix H (ASTM E-185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels) will require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance.
 
Discussion Plant technical specifications often direct licensees to conduct testing and surveillance of material specimens according to Appendix H. Appendix H, in tum, requires withdrawal schedules to meet an applicable ASTM standard. In this instance, as long as the plant's withdrawal schedule change meets the applicable ASTM standard, the plant will not be           l
    ~9~92?0       PK W UO               q1011r                                         -vW ,
 
AL 97-04 September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.
 
However, if the plant's withdrawal schedule change does not meet the applicable ASTM
standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.
 
Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.
 
==Backfit Discussion==
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC
licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.
 
This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
I  is:-Roe, Acting Director of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR
            301-415-3027 E-mail: jbhl @nrc.gov Attachment: List of Recently Issued Administrative Letters
 
V
                                                                        Attachment AL 97-04 September 30, 1997 LIST OF RECENTLY ISSUED
                                      NRC ADMINISTRATIVE LETTERS
Administrative                                      Date of Letter No.              Subject                    Issuance    Issued to
97-03            Plant Restart Discussions          03/28/97    All holders of OLs or CPs Following Natural Disasters                    for nuclear power reactors
97-02            Elimination of National            03/06/97    All holders of OLs or CPs Examination Schedule for                        for nuclear power reactors Operator Licensing
97-01            State Initiatives to              01/17/97    All holders of OLs or Legalize Schedule 1                            for nuclear power reactors Drugs                                          and all licensees authorized to possess or transport Category 1 nuclear material
96-05            Compliance with the                11/05196    All material and fuel Rule"Timeliness in                            cycle licensees Decommissioning of Material Facilities"
96-04            Efficient Adoption of              10/09/96    All holders of OLs for Improved Standard Tech-                        nuclear power reactors nical Specifications                          who have not converted to the improved standard technical specifications
96-03            Centralization of Quality          09/27/96    All holders of OLs or CPs Assurance Program Review                        for nuclear power reactors Responsibility in the Office of Nuclear Reactor Regulation
95-03,          Availability of Reactor            07/10/96    All holders of OLs or CPs Rev. 1          Vessel Integrity Database                      for nuclear power reactors
96-02            Licensee Responsibilities          06/21/96    All holders of OLs or CPs Related to Financial Quali-                    for nuclear power reactors fications OL = Operating License CP = Construction Permit
 
AL 97-04 September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.
 
However, if the plant's withdrawal schedule change does not meet the applicable ASTM
          standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.
 
Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.
 
==Backfit Discussion==
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC
            licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.
 
This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
original signed by Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR
                        301-415-3027 E-mail: jbhl @nrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: 97-04.AL                      *SEE PREVIOUS CONCURRENCES
To receive a copy of this document, Indicate In the box: "C" =Copy without enclosures _E" - Copy with enclosures "N =  No copy    -
OFFICE PD3-3:PM                I E PD3-3:LA              I N IOGC                  I      PD3-3:D          I      PECB      I
NAME          JHopkins*                CBoyle*                STurk*                      GMarcus*                CPetrone*
DATE          08/05/97                  08/04/97                08/07/97                    08/19/97                08/21/97 (A)C:PECB I            IDE:EMCB          I(A)Q FFPM 1I
RDennig*                IEJSullivan* JREX ,
08/22/97                09/23/97          09/- 197    ---
                                                                    Mrr^nnr    rrtenv Urrl-IWAL KLLUKU        LUOT
 
AL 97-04 September 18, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.
 
However, if the plant's withdrawal schedule change does not meet the applicable ASTM
            standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.
 
Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.


==Backfit Discussion==
==Backfit Discussion==
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to thisadministrative letter. This information is being provided in light of the Memorandum andOrder and does not constitute a backfit in that the substance of the regulations is not beingchanged in any respect by this action, and no substantive regulatory requirements that aredifferent from or greater than those that existed heretofore are being imposed on NRClicensees. This administrative letter does not involve any provisions that would imposebackfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.This administrative letter requires no specific action or written response. If you have anyquestions about this matter, please contact the lead project manager listed below or yourappropriate Office of Nuclear Reactor Regulation (NRR) project manager.I is:-Roe, Acting Directorof Reactor Program ManagementOffice of Nuclear Reactor RegulationContact: Jon Hopkins, NRR301-415-3027E-mail: jbhl @nrc.govAttachment: List of Recently Issued Administrative Letters VAttachmentAL 97-04September 30, 1997 LIST OF RECENTLY ISSUEDNRC ADMINISTRATIVE LETTERSAdministrative Date ofLetter No. Subject Issuance Issued to97-0397-0297-0196-0596-04Plant Restart DiscussionsFollowing Natural DisastersElimination of NationalExamination Schedule forOperator LicensingState Initiatives toLegalize Schedule 1DrugsCompliance with theRule"Timeliness inDecommissioning ofMaterial Facilities"Efficient Adoption ofImproved Standard Tech-nical SpecificationsCentralization of QualityAssurance Program ReviewResponsibility in theOffice of Nuclear ReactorRegulationAvailability of ReactorVessel Integrity DatabaseLicensee ResponsibilitiesRelated to Financial Quali-fications03/28/9703/06/9701/17/9711/0519610/09/9609/27/9607/10/9606/21/96All holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs orfor nuclear power reactorsand all licensees authorizedto possess or transportCategory 1 nuclear materialAll material and fuelcycle licenseesAll holders of OLs fornuclear power reactorswho have not convertedto the improved standardtechnical specificationsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactors96-0395-03,Rev. 196-02OL = Operating LicenseCP = Construction Permit AL 97-04September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a licenseamendment would not be required, although prior NRC approval to verify conformance withthe ASTM standard is required by Appendix H.However, if the plant's withdrawal schedule change does not meet the applicable ASTMstandard, then the change will be treated as a license amendment requiring public notice andopportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in suchsubmittals.
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC
            licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.
 
This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR
                        301-415-3027 E-mail: jbhlnrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: 97-04.AL
To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE        PD3-3:PM            E PD3-3:LA              N OGC                            PD3-3:D                  PECB      I
INAME          J[Hopkins*                CBoyle*                  STurk*                      GMarcus*                CPetrone*
IDATE          08/05/97                  08/04/97                08/07/97                    08/19/97                  08/21/97 (A)C:PECB                (A)D:DRPM
RDennig*                JRoe
08/22/97                09/ /97 OFFICIAL RECORD COPY
 
AL 97-XX
                                                                                                        August, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.
 
However, if the plant's withdrawal schedule change does not meet the applicable ASTM
            standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.
 
Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.


==Backfit Discussion==
==Backfit Discussion==
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to thisadministrative letter. This information is being provided in light of the Memorandum andOrder and does not constitute a backfit in that the substance of the regulations is not beingchanged in any respect by this action, and no substantive regulatory requirements that aredifferent from or greater than those that existed heretofore are being imposed on NRClicensees. This administrative letter does not involve any provisions that would imposebackfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.This administrative letter requires no specific action or written response. If you have anyquestions about this matter, please contact the lead project manager listed below or yourappropriate Office of Nuclear Reactor Regulation (NRR) project manager.original signed byJack W. Roe, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationContact: Jon Hopkins, NRR301-415-3027E-mail: jbhl @nrc.govAttachment: List of Recently Issued Administrative LettersDOCUMENT NAME: 97-04.AL *SEE PREVIOUS CONCURRENCESTo receive a copy of this document, Indicate In the box: "C" = Copy without enclosures _E" -Copy with enclosures "N = No copy-OFFICE PD3-3:PM I E PD3-3:LA I N IOGC I PD3-3:D I PECB INAME JHopkins* CBoyle* STurk* GMarcus* CPetrone*DATE 08/05/97 08/04/97 08/07/97 08/19/97 08/21/97(A)C:PECB I IDE:EMCB I(A)Q FFPM 1IRDennig* IEJSullivan* JREX ,08/22/97 09/23/97 09/- 197 ---Mrr^nnr rrtenvUrrl-IWAL KLLUKU LUOT
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC
AL 97-04September 18, 1997 AL 97-XXAugust, 1997 AL 97-XXAugust x, 1997 
            licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.
}}
 
This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR
                          301-415-3027 E-mail: jbhl@nrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: G:\CDP\ADMI.LTR
To receive a copy of this document, Indicate In the box: "C' = Copy without enclosures 'En = Copy with enclosures "N" = No copy OFFICE         PD3-3:PM         I E       PD3-3:LA       I N OGC                    I       PD3-3:D           l      PECB      I
  NAME        JHopkins*                   CBoyle*               STurk*                     GMarcus*                 CPetrone*
  DATE         08/05/97                   08/04/97A              08/07/97                   08/19/97                 08/21/97   .
I*kA)L.:rtLLb A I
                  I
                        I        rnrnkI
                          lkM)U:UKrm I
                                        1111 I
                                                  _k RDennig*                                     mJRoeIR
08/22/97                 108/ /97
        7 7Jo      ] q7                  f            OFFICIAL RECORD COPY
 
AL 97-XX
                                                                                                            August x, 1997 However, iKthe plant's withdrawal schedule change does not meet the applicable ASTM
            standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.
 
Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.
 
==Backfit Discussion==
The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC
              licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.
 
This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
 
Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR
                          (301) 415-3027 E-mail: JBH1@nrc.gov DOCUMENT NAME: G:XCDP\ADMI.LTR
To receive a copy of this document, Indicate in the box: IC' a Copy without enclosures "E" - Copy with enclosures "N' u No copy OFFICE fPD3-3:PM              IE      PD3-3:LA        I N OGC                    I      PD3-3:D          I        PECB    X
NAME            JHopkins*              CBoyl e*                STurk*                      GMarcus*                  CPetrone DATE            08/05/97                08/04/97                08/07/97                    08/19/97                 08/ 97 (A)C:PEW 4                (A)D:DRPM    7I l RDenni 6/1- -' INJRoe
  8/
02    -1 9 7            708/    /97 OFFICIAL RECORD COPY}}


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Latest revision as of 02:17, 24 November 2019

NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
ML031210296
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River, Crane  Entergy icon.png
Issue date: 09/30/1997
From: Roe J
Office of Nuclear Reactor Regulation
To:
References
GL-97-004, NUDOCS 9709290106
Download: ML031210296 (7)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 September 30, 1997 NRC ADMINISTRATIVE LETTER 97-04: NRC STAFF APPROVAL FOR CHANGES TO

10 CFR PART 50, APPENDIX H, REACTOR

VESSEL SURVEILLANCE SPECIMEN

WITHDRAWAL SCHEDULES

Addressees

All holders of operating licenses for nuclear power reactors except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to inform licensees that changes to their facilities' reactor vessel surveillance specimen capsule withdrawal schedules as specified in Appendix H to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) that do not conform to the required ASTM standard referenced in Appendix H will be treated as license amendments requiring public notice and opportunity for a hearing.

Background In a Memorandum and Order (CLI-96-13) issued in the Perry operating license amendment proceeding on December 6, 1996, the Commission reversed and vacated the Atomic Safety and Licensing Board Order, LBP-95-17, which required that all future proposed withdrawal schedule changes be treated as license amendments. The Commission found that while

10 CFR Part 50, Appendix H, II.B.3 requires prior NRC approval for all withdrawal schedule changes, only certain changes require license amendments as the process to be followed for such approval. Specifically, those changes that do not conform to the ASTM standard referenced in Appendix H (ASTM E-185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels) will require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance.

Discussion Plant technical specifications often direct licensees to conduct testing and surveillance of material specimens according to Appendix H. Appendix H, in tum, requires withdrawal schedules to meet an applicable ASTM standard. In this instance, as long as the plant's withdrawal schedule change meets the applicable ASTM standard, the plant will not be l

~9~92?0 PK W UO q1011r -vW ,

AL 97-04 September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.

However, if the plant's withdrawal schedule change does not meet the applicable ASTM

standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.

Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.

Backfit Discussion

The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC

licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.

This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

I is:-Roe, Acting Director of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR

301-415-3027 E-mail: jbhl @nrc.gov Attachment: List of Recently Issued Administrative Letters

V

Attachment AL 97-04 September 30, 1997 LIST OF RECENTLY ISSUED

NRC ADMINISTRATIVE LETTERS

Administrative Date of Letter No. Subject Issuance Issued to

97-03 Plant Restart Discussions 03/28/97 All holders of OLs or CPs Following Natural Disasters for nuclear power reactors

97-02 Elimination of National 03/06/97 All holders of OLs or CPs Examination Schedule for for nuclear power reactors Operator Licensing

97-01 State Initiatives to 01/17/97 All holders of OLs or Legalize Schedule 1 for nuclear power reactors Drugs and all licensees authorized to possess or transport Category 1 nuclear material

96-05 Compliance with the 11/05196 All material and fuel Rule"Timeliness in cycle licensees Decommissioning of Material Facilities"

96-04 Efficient Adoption of 10/09/96 All holders of OLs for Improved Standard Tech- nuclear power reactors nical Specifications who have not converted to the improved standard technical specifications

96-03 Centralization of Quality 09/27/96 All holders of OLs or CPs Assurance Program Review for nuclear power reactors Responsibility in the Office of Nuclear Reactor Regulation

95-03, Availability of Reactor 07/10/96 All holders of OLs or CPs Rev. 1 Vessel Integrity Database for nuclear power reactors

96-02 Licensee Responsibilities 06/21/96 All holders of OLs or CPs Related to Financial Quali- for nuclear power reactors fications OL = Operating License CP = Construction Permit

AL 97-04 September 30, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.

However, if the plant's withdrawal schedule change does not meet the applicable ASTM

standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.

Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.

Backfit Discussion

The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC

licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.

This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

original signed by Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR

301-415-3027 E-mail: jbhl @nrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: 97-04.AL *SEE PREVIOUS CONCURRENCES

To receive a copy of this document, Indicate In the box: "C" =Copy without enclosures _E" - Copy with enclosures "N = No copy -

OFFICE PD3-3:PM I E PD3-3:LA I N IOGC I PD3-3:D I PECB I

NAME JHopkins* CBoyle* STurk* GMarcus* CPetrone*

DATE 08/05/97 08/04/97 08/07/97 08/19/97 08/21/97 (A)C:PECB I IDE:EMCB I(A)Q FFPM 1I

RDennig* IEJSullivan* JREX ,

08/22/97 09/23/97 09/- 197 ---

Mrr^nnr rrtenv Urrl-IWAL KLLUKU LUOT

AL 97-04 September 18, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.

However, if the plant's withdrawal schedule change does not meet the applicable ASTM

standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.

Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.

Backfit Discussion

The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC

licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.

This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR

301-415-3027 E-mail: jbhlnrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: 97-04.AL

To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE PD3-3:PM E PD3-3:LA N OGC PD3-3:D PECB I

INAME J[Hopkins* CBoyle* STurk* GMarcus* CPetrone*

IDATE 08/05/97 08/04/97 08/07/97 08/19/97 08/21/97 (A)C:PECB (A)D:DRPM

RDennig* JRoe

08/22/97 09/ /97 OFFICIAL RECORD COPY

AL 97-XX

August, 1997 exceeding the operating authority already granted in its license. Therefore, a license amendment would not be required, although prior NRC approval to verify conformance with the ASTM standard is required by Appendix H.

However, if the plant's withdrawal schedule change does not meet the applicable ASTM

standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.

Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.

Backfit Discussion

The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC

licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.

This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR

301-415-3027 E-mail: jbhl@nrc.gov Attachment: List of Recently Issued Administrative Letters DOCUMENT NAME: G:\CDP\ADMI.LTR

To receive a copy of this document, Indicate In the box: "C' = Copy without enclosures 'En = Copy with enclosures "N" = No copy OFFICE PD3-3:PM I E PD3-3:LA I N OGC I PD3-3:D l PECB I

NAME JHopkins* CBoyle* STurk* GMarcus* CPetrone*

DATE 08/05/97 08/04/97A 08/07/97 08/19/97 08/21/97 .

I*kA)L.:rtLLb A I

I

I rnrnkI

lkM)U:UKrm I

1111 I

_k RDennig* mJRoeIR

08/22/97 108/ /97

7 7Jo ] q7 f OFFICIAL RECORD COPY

AL 97-XX

August x, 1997 However, iKthe plant's withdrawal schedule change does not meet the applicable ASTM

standard, then the change will be treated as a license amendment requiring public notice and opportunity for a hearing in accordance with Section 189a of the Atomic Energy Act.

Therefore, the information required by 10 CFR 50.91 and 50.92 should be included in such submittals.

Backfit Discussion

The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this administrative letter. This information is being provided in light of the Memorandum and Order and does not constitute a backfit in that the substance of the regulations is not being changed in any respect by this action, and no substantive regulatory requirements that are different from or greater than those that existed heretofore are being imposed on NRC

licensees. This administrative letter does not involve any provisions that would impose backfits as defined in 10 CFR 50.109(a)(1), and a backfit analysis is, therefore, not required.

This administrative letter requires no specific action or written response. If you have any questions about this matter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Contact: Jon Hopkins, NRR

(301) 415-3027 E-mail: JBH1@nrc.gov DOCUMENT NAME: G:XCDP\ADMI.LTR

To receive a copy of this document, Indicate in the box: IC' a Copy without enclosures "E" - Copy with enclosures "N' u No copy OFFICE fPD3-3:PM IE PD3-3:LA I N OGC I PD3-3:D I PECB X

NAME JHopkins* CBoyl e* STurk* GMarcus* CPetrone DATE 08/05/97 08/04/97 08/07/97 08/19/97 08/ 97 (A)C:PEW 4 (A)D:DRPM 7I l RDenni 6/1- -' INJRoe

8/

02 -1 9 7 708/ /97 OFFICIAL RECORD COPY

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