GNRO-2009/00060, Request to Use Portion of Later Edition to the American Society of Mechanical Engineers Code for Operation & Maintenance of Nuclear Power Plants for Main Steam Safety Relief Valve Inservice Testing
| ML092960344 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/22/2009 |
| From: | Perino C Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2009/00060 | |
| Download: ML092960344 (5) | |
Text
GNRO-2009/00060 Octo U.S
. Nuclear Regulatory Commission Attention - Document Control Desk Washington, D.C
. 20555-0001 SUBJ REFERENC De per 22,2009 Madam : -
Request to Use Portion of Later Edition to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants for Main Steam Safety Relief Valve Inservice Testing Grand Gulf Nuclear ocket No. 50-416 License No.
NRC Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Sectio XI," dated July 28, 2004 tation, Unit Pursuant to 10CFR50.55a(f)(4)(Iv) and in accordance with the guidance provided NRC RIS 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," (Reference 1), Entergy Operations, Inc
. (Entergy) requests approval to use a portion of a later code edition of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM ode) for the Grand Gulf Nuclear Station (GGNS) Inservice Testing (IST) Program.
Specifically, Entergy requests approval to implement Mandatory Appendix 1, Paragraph 1-3410(d) of the 2004 Edition of the ASME OM Code at GGNS for Main Steam Safet Relief Valve Inservice Testing.
Paragraph 10CFR50.55a(f)(4)(ii) requires the use of the latest edition and addenda that have been incorporated by reference 12 months prior to the beginning of each 120-month interval, For GGNS, the current 120-month interval uses the 2001 Edition of the ASME OM Code through 2003 Addenda. Licensees that plan to use for their IST program later editions and addenda of the ASME OM Code that have been incorporated by reference into 10CFR50.55a must submit a request for NRC approval pursuant to I 0CFR50.55a(f)(4)(iv) prior to its use, As noted in NRC RIS 2004-12, licensees seeking to use later editions and addenda of the ASME OM Code, pursuant to 1 0CFR50.55a(f)(4)(1v) for inservice testing items are not required to seek alternatives pursuant to 10CFR50,55a(a)(3) or relief pursuant to 1 0CFR50a(f)(5)(1v).
1
GNRO-2009/00060 Page 2 of 2 The request is detailed in the attachment to this letter Entergy requests approval of this request by March 15, 2010, to support testing planned for the seventeenth refueling outage (RF-17),, which is currently scheduled to begin in Spring of 2010.
This letter contains no commitments. Should you have any questions regarding this submittal, please contact Michael Larson, at 601-437-6685.
Sincerely,
'tachment,
10CFR50.55a Request Number GGNS-2009-01, Refueling Outage 17 Main Steam Safety Relief Valve Inservice Testing NRC Senior Resident Inspector Grand Gulf Nuclear Station son, MS 39150 clear Regulatory Commissio ATTN - Mr. Elmo E. Collins (wla}
Regional Administrator, Region I 12 East Lamar Drive, Suite 4 Arlington, TX 76011-4005
.S
. Nuclear Regulatory Commissio ATTN.- Mr. Carl F. Lyon, NRR/ADRO/DORL Mail Stop OVVFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 cc:
an Attachment GNRO-2009/00060 OCFR50.55a Request Number GGNS-2009-
,efueling Outag team Safety Relief Valve Inservice Testing to GNRO-2009/00060 10CFR50.55a Request Number GGNS-2009-01 Refueling Outage 17 Main Steam Safety Relief Valve Inservice Testing to GNRO-2009/00060 10CFR50.55a Request Number GGNS-2009-01 Refueling Outage 17 Main Steam Safety Relief Valve Inservice Testing
Attachment to GNRO-2009100060 Page 1 of 2 Request in Accordance with 10 CFR 50.55a(f)(4)(iv)
For Use of Subsequent ASME Code Edition and Addenda Pursuant to 10CFR 50.55a(f)(4)(iv) and in accordance with the guidance provided in NRC Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) and Section XI," Entergy Operations, Inc.
(Entergy) requests approval to use a portion of a later code edition of the ASME OM Code for the Grand Gulf Nuclear Station (GGNS) Inservice Testing (IST) Program.
Specifically, Entergy requests approval to implement Mandatory Appendix I, Paragraph I-3410(d) of the 2004 Edition of the ASME OM Code at GGNS for Main Steam Safety Relief Valve Inservice Testing.
PLANT/UNIT GGNS, Unit 1 INTERVAL :
Third 10 Year Inservice Testing Interval ASME CODE Main Steam Safety Relief Valve (20 valves installed)
COMPONENTS AFFECTED :
Model :
-471 Manufacturer : Dikkers Valves APPLICABLE For GGNS, the current 120-month IST program interval uses the 2001 CODE EDITION Edition of the ASME OM Code through the 2003 Addenda, which AND ADDENDA:
includes the following (from Mandatory Appendix I) requirement:
1-3404 Disposition After Testing or Maintenance 1-3410 Class l Main Steam Pressure Relief Valves With Auxiliary Actuating Devices (d) Each valve that has been maintained or refurbished in place, removed for maintenance and testing, or both, and reinstalled shall be remotely actuated at reduced or normal system pressure to verify open and close capability of the valve before resumption of electric power generation. Set-pressure verification is not required.
P NT/UNIT:
INTERV ASME CODE COMPONENTS AFFECTED:
installed)
Model: G-471 120-month program interval uses OM through the 2003 Add which (from Mandatory Appendix I) 1-3400 Disposition After Testing or Maintenance Manufacturer: Dikkers "r--:lI'llL-JiL:'
APPLICABLE CODE EDITION AND ADDENDA:
P NT/UNIT:
INTERV ASME CODE COMPONENTS AFFECTED:
installed)
Model: G-471 120-month program interval uses OM through the 2003 Add which (from Mandatory Appendix I) 1-3400 Disposition After Testing or Maintenance Manufacturer: Dikkers "r--:lI'llL-JiL:'
APPLICABLE CODE EDITION AND ADDENDA:
Attachment to GNRO-2009100060 Page 2 of 2 Request in Accordance with 10 CFR 50.55a(f)(4)(iv)
For Use of Subsequent ASME Code Edition and Addenda PROPOSED Entergy requests approval to use a portion of Mandatory Appendix I to SUBSEQUENT
~'the 2004 Edition of the ASME OM Code at GGNS for Main Steam CODE EDITION Safety Relief Inservice Testing. Federal Register, Volume 73, Number AND ADDENDA 176, dated September 10, 2008 (73 FR 52730), incorporates by (OR PORTION) :
reference the 2004 Edition of the ASME OM Code in 10CFR50.55a(b)(3). The specific paragraph to be used is I-3410(4),
which is copied as follows :
1-3400 Disposition After Testing or Maintenance 1-3410 Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices (d) Each valve with an auxiliary actuating device that has been removed for maintenance or testing and reinstalled after meeting the requirements of 1-3310, shall have the electrical and pneumatic connections verified either through mechanical l electrical inspection or test prior to the resumption of electric power generation. Main disc movement and set-pressure verification are not required.
RELATED 10CFR50.55a(f)(4)(iv) states :
REQUIREMENTS :
Inservice tests of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
The requirements of Mandatory Appendix I, Paragraph I-3410(4) of the 2004 Edition of the ASME OM Code are not modified by 10CFR50.55a(b).
Reviews of differences between our current Code of Record, 2001 Edition of the ASME OM Code through the 2003 Addenda, and the 2004 Edition of the ASME OM Code did not result in identification of any related requirements to Mandatory Appendix I, Paragraph I-3410(4).
DURATION OF The duration of the proposed request is for the remainder of GGNS's PROPOSED Third 10 Year Inservice Testing Interval, which began on December 1, REQUEST:
2007, and ends on November 30, 2017.
3 STATUS :
r Submitted for Nuclear Regulatory Commission approval 1-3400 DiSDO~;/t/c)n
'estlno or Maintencin(~e RELATED 1
REQUIREMENTS:
1-3400 DiSDO~;/t/c)n
'estlno or Maintencin(~e RELATED 1
REQUIREMENTS: