NRC Generic Letter 1983-15: Difference between revisions

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{{#Wiki_filter:Q'-0 i.r I: March 23, 1983 TO ALL LICENSEES
{{#Wiki_filter:0           i.
OF OPERATING
POWER REACTORS AND APPLICANTS
FOR OPERATING LICENSES (GENERIC LE1TER 83-15)SUBJECT: IMPLEMENTATION
OF REGULATORY
GUIDE 1.150, "ULTRASONIC
TESTING OF REACTOR VESSEL WELDS DURING PRESERVICE
AND INSERVICE
EXAMINATIONS, REVISION 1 " The original version of Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," dated June 1981, was reviewed by the Ad Hoc Committee of the Electric Utility Industry.


The Comnittee's review resulted in their recommending an alternative method, which was presented in 'Final Report -Reconmended Changes to Regulatory Guide 1.150,'August 1982.The NRC staff has evaluated the recommended alternative method in the report and finds it an acceptable alternative.
Q'-
            r                    I:
                                                                      March 23, 1983 TO ALL LICENSEES OF OPERATING POWER REACTORS AND APPLICANTS FOR OPERATING
                  LICENSES (GENERIC LE1TER 83-15)
                  SUBJECT:              IMPLEMENTATION OF REGULATORY GUIDE 1.150, "ULTRASONIC TESTING OF
                                        REACTOR VESSEL WELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS,
                                        REVISION 1 "
                  The original version of Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," dated June 1981, was reviewed by the Ad Hoc Committee of the Electric Utility Industry. The Comnittee's review resulted in their recommending an alternative method, which was presented in 'Final Report - Reconmended Changes to Regulatory Guide 1.150,'
                August 1982.


Therefore, this alternative method has been added to the regulatory positions in Regulatory Guide 1.150, and this Revision 1 Is being issued as an active guide without prior issuance as a draft guide for comnent.Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Co-mission's regu-lations, the method described in Revision I of the subject Guide will be used in the evaluation of (1) the results of inservice examination programs of all oper-ating reactors after July 15, 1981, and (2) the results of preservice examination program of all reactors under construction performed after January 15, 1982. The reconmendations of this guide are not intended to apply to preservice examinations that have already been completed.
The NRC staff has evaluated the recommended alternative method in the report and finds it an acceptable alternative. Therefore, this alternative method has been added to the regulatory positions in Regulatory Guide 1.150, and this Revision 1 Is being issued as an active guide without prior issuance as a draft guide for comnent.


We recommend that all licensees modify their technical specifications if appropriate, to make them consistent with the recom-mendations in the subject Guide.Any guidance in the subject Guide related to information collection activities has been cleared under OM Clearance No. 3150-0011, which expires April 30, 1985.Sincerely, I Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation OIVAI$ "-6-9, is zl-7 DL MWillaim 1'83 40aap-.10rl on --- --1010, I9a WJohnst Gn G as .k ...... nhut SURKAME~ .. .. ***...*........  
Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Co-mission's regu- lations, the method described in Revision I of the subject Guide will be used in the evaluation of (1) the results of inservice examination programs of all oper- ating reactors after July 15, 1981, and (2) the results of preservice examination program of all reactors under construction performed after January 15, 1982. The reconmendations of this guide are not intended to apply to preservice examinations that have already been completed. We recommend that all licensees modify their technical specifications if appropriate, to make them consistent with the recom- mendations in the subject Guide.
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I
                  Any guidance in the subject Guide related to information collection activities has been cleared under OM Clearance No. 3150-0011, which expires April 30, 1985.
 
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation OIVAI$                   "                                                                                   -6-9, DL
                                                                                                                    MWillaimis
                -   .10rl---on
                                  40aap
                                    --                                                                 1010,     1'83              zl-7 SURKAME~    I9a                                 .. ..WJohnst
                                                            ***...*........ Gn G..   as          1.. k                ......       nhut OATE~ .22fi*183             ..     .               .. 1.I. 8..... ... .43
                                                                              .       ....... J3 4 a       .... *K ...     ______....
.R OM 11-80 ___._024                                    OFICA               REOR           COP                           USW   91-3- NR C FORM 3l18 (10-80) NACM 0240                         OFFICIAL           RECORD COPY                                     usaPO 195--35t}}


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Latest revision as of 04:16, 24 November 2019

NRC Generic Letter 1983-015: Implementation of Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice & Inservice Examinations, Revision 1.
ML031080381
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, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, 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, 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, 05000514, 05000000, 05000496, 05000497, 05000515, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Cherokee, Clinch River, Skagit, Marble Hill, Black Fox
Issue date: 03/23/1983
From: Eisenhut D
Office of Nuclear Reactor Regulation
To:
References
RG-1.150, Rev 1 GL-83-015, NUDOCS 8303040008
Download: ML031080381 (1)
v • d • e


0 i.

Q'-

r I:

March 23, 1983 TO ALL LICENSEES OF OPERATING POWER REACTORS AND APPLICANTS FOR OPERATING

LICENSES (GENERIC LE1TER 83-15)

SUBJECT: IMPLEMENTATION OF REGULATORY GUIDE 1.150, "ULTRASONIC TESTING OF

REACTOR VESSEL WELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS,

REVISION 1 "

The original version of Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," dated June 1981, was reviewed by the Ad Hoc Committee of the Electric Utility Industry. The Comnittee's review resulted in their recommending an alternative method, which was presented in 'Final Report - Reconmended Changes to Regulatory Guide 1.150,'

August 1982.

The NRC staff has evaluated the recommended alternative method in the report and finds it an acceptable alternative. Therefore, this alternative method has been added to the regulatory positions in Regulatory Guide 1.150, and this Revision 1 Is being issued as an active guide without prior issuance as a draft guide for comnent.

Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Co-mission's regu- lations, the method described in Revision I of the subject Guide will be used in the evaluation of (1) the results of inservice examination programs of all oper- ating reactors after July 15, 1981, and (2) the results of preservice examination program of all reactors under construction performed after January 15, 1982. The reconmendations of this guide are not intended to apply to preservice examinations that have already been completed. We recommend that all licensees modify their technical specifications if appropriate, to make them consistent with the recom- mendations in the subject Guide.

I

Any guidance in the subject Guide related to information collection activities has been cleared under OM Clearance No. 3150-0011, which expires April 30, 1985.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation OIVAI$ " -6-9, DL

MWillaimis

- .10rl---on

40aap

-- 1010, 1'83 zl-7 SURKAME~ I9a .. ..WJohnst

      • ...*........ Gn G.. as 1.. k ...... nhut OATE~ .22fi*183 .. . .. 1.I. 8..... ... .43

. ....... J3 4 a .... *K ... ______....

.R OM 11-80 ___._024 OFICA REOR COP USW 91-3- NR C FORM 3l18 (10-80) NACM 0240 OFFICIAL RECORD COPY usaPO 195--35t

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