NRC Generic Letter 1997-04: Difference between revisions
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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 | | author name = Roe J | ||
| author affiliation = NRC/NRR | | author affiliation = NRC/NRR | ||
| addressee name = | | addressee name = | ||
Revision as of 04:42, 14 July 2019
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 97-02 97-01 96-05 96-04 Plant Restart Discussions Following Natural Disasters Elimination of National Examination Schedule for Operator Licensing State Initiatives to Legalize Schedule 1 Drugs Compliance with the Rule"Timeliness in Decommissioning of Material Facilities" Efficient Adoption of Improved Standard Tech-nical Specifications Centralization of Quality Assurance Program Review Responsibility in the Office of Nuclear Reactor Regulation Availability of Reactor Vessel Integrity Database Licensee Responsibilities Related to Financial Quali-fications 03/28/97 03/06/97 01/17/97 11/05196 10/09/96 09/27/96 07/10/96 06/21/96 All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or for nuclear power reactors and all licensees authorized to possess or transport Category 1 nuclear material All material and fuel cycle licensees All holders of OLs for nuclear power reactors who have not converted to the improved standard technical specifications All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors 96-03 95-03, Rev. 1 96-02 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* A I rnrnkI I 1111 I kA)L.:rtLLb I lkM)U:UKrm I_k RDennig* mJRoeI 08/22/97 108/ /97 7 7Jo ] q 7 f OFFICIAL RECORD COPY
AL 97-XX August x, 1997 However, iK 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: 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
I E 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- -' I NJRoe 0 8/2-1 9 7 708/ /97 OFFICIAL RECORD COPY