ML20140G959: Difference between revisions

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#REDIRECT [[LR-N970332, Provides Insp/Evaluation/Repairs Plans for Core Shroud IAW Commitments in 940824 & s.Suppl Response to GL 94-03, Core Shroud Insp,Evaluation & Repair Plans, Encl]]
| number = ML20140G959
| issue date = 06/09/1997
| title = Provides Insp/Evaluation/Repairs Plans for Core Shroud IAW Commitments in 940824 & 950331 Ltrs.Suppl Response to GL 94-03, Core Shroud Insp,Evaluation & Repair Plans, Encl
| author name = Storz L
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000354
| license number =
| contact person =
| document report number = GL-94-03, GL-94-3, LR-N970332, NUDOCS 9706170231
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 6
}}
 
=Text=
{{#Wiki_filter:-      . _ _ .      . -    . -      _          - .      . - - . -            .    - . - - - . .              .
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                          '                                                                                                                        I Pubhc Senace Electne and Gas                                                                ;
Cornpany l
Loub F. Storz                              Public Service Electric and Gas Company        P.O. Box 236, Hancocks Bridge. NJ 08038 609-339-5700 Sernor Vce Pres: dent - Nuclear Operation.
JUN 0 91997 LR-N970332 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUFiLEMENTAL PESPONSE TO GENERIC LETTER 94-03 CORE SHROUD IMJPECTION, EVALUATION, AND REPAIR PLANS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Ladies and Gentlemen:
On July 25, 1994, the NRC issued Generic Letter 94-03, "Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors." Public Service Electric and Gas Company                                                                !
(PSE&G) submitted an initial response to the generic letter on                                                              1 August 24, 1994 and a supplemental response on March 31, 1995.
i                    These responses committed to providing plans for inspection and                                                                I l                      for evaluation and/or repair of the core shroud no later than                                                                )
l                    three months prior to performing the inspections.                                            PSE&G plans to conduct the inspections during the seventh refueling outage scheduled for September 1997. This letter provides the inspection / evaluation / repairs plans for the core shroud in accordance with the commitments in the previous letters.                                                    The attachment to this letter contains detailed information on PSE&G's plans.
Should you have any questions regarding this request, we will be pleased to discuss them with you.
                                                                                                                                          /
I Sincerely, h
Affidavit Attachment 9706170231 970609 PDR        ADOCK 05000354
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Document Control Desk                    LR-N970332                                        JUN 0 91997 C    Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North                                            1 11555 Rockville Pike Mail Stop 14E21                                                  )
1 Rockville, MD 20852                                              '
l Mr. S. Morris (X24)                                              l USNRC Resident Inspector - HC                                    1 Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering                                    )
l 33 Arctic Parkway                                                l CN 415 Trenton, NJ  08625 l
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4 REF: LR-N970332 STATE OF NEW JERSEY )
                              )  SS.
COUNTY OF SALEM      )
L. F. Storz, being duly sworn according to law deposes and says:
I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Hope Creek Generating Station, Unit 1, are true to the best of my knowledge, information and belief.
                                ;    '$50 Subscribed and Sw r    to before me this /O d;A day of'nqLL -        ,  1997
            ,/'
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{hM  di /        BELL i^.--
potary Put'1td of New Jersey                                            i 1
KIMBERLY JO BROWN UWY PUBLIC Of NEW JERSEY My Commission expires on            "' C"*"",ssi n Empires April 21,1993 i l
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          -.-    -        .  .--        ..  . - - -  --    . - - - . -    -    - - _ ~
  ,          Document Contro] Dzak                                          LR-N970332 Attachment HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354                                    '
CORE SHROUD INSPECTION, EVALUATION, AND REPAIR PLANS In accordance with NRC Generic Letter (GL) 94-03, dated July 25, 1994, the core shroud inspection plan for Hope Creek is provided below. The plan has been developed for implementation during Hope Creek's seventh refueling outage (RFO7), which is scheduled                ,
to begin in September 1997.
The inspection methods, scope, and flaw evaluation criteria of this inspection plan satisfy the recommendations of the Boiling Water Reactor Vessel Internals Project (BWRVIP), as specified in the "BWR Core Shroud Inspection and Flaw Evaluation Guidelines" (BWRVIP-01) - Revision 2.
This inspection plan has been developed using the ongoing guidance provided by the BWRVIP, the recommendations of General Electric Company Service Information Letter (SIL) 572, and site specific experience gained through previous shroud inspections at Hope Creek. The key factors considered in the development of the plan include:  hot operating years, materials, water chemistry history, fabrication processes, neutron fluence, available inspection techniques, accessibility, equipment, logistics of                  i data evaluation and stress corrosion cracking history at Hope                    l Creek.                                                                          1 The Hope Creek shroud is considered to have limited, but low, potential for Intergranular Stress Corrosion Cracking (IGSCC);
due primarily to material, age, and water chemistry history.
Since the Hope Creek core shroud has experienced more than eight hot operating years, sad is fabricated with low carbon content stainless steel, Hope Creek had been identified by BWRVIP-01 as
!              an Inspection Category B facility. For Inspection Category B i              facilities, BWRVIP-01 recommends a limited inspection of H-3, H-L              4, H-5 and H-7 shroud welds. Since Hope Creek intends to use the longest re-inspection interval allowed by the "BWRVIP Guidelines For Reinspection of BWR Core Shrouds" (BWRVIP-07), an examination of 100% of the accessible lengths of circumferential welds H-3, H-4, H-5 and H-7 will be performed.
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                                  ~
      ,                Document Control Dask                                                LR-N970332 Attachment                                                                            ,
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                      -SCOPE OF INSPECTION:-
The Hope Creek shroud welds can be divided into four groups:
: 1. Shroud attachment welds (e.g. shroud head bolt lugs)                              !
l2. Shroud vertical welds
: 3. Shroud support structure welds
: 4. Shroud circumferential welds The shroud attachment welds, vertical welds, and support                            i structure welds have not been included in the initial inspection'                    -
                      ' plan. As indicated in Section 3.1 of BWRVIP-01, the safety consequences of degradation of the shroud attachment welds are considerably less significant than those associated with the circumferential welds and inspection of these welds is not currently required. The basis for not including the vertical welds is addressed in Section 3.11 and Appendix A of BWRVIP-01.
The shroud support structure welds have not been included since these' welds are considered to be less susceptible to cracking than the shroud welds. The reduced susceptibility is based on the following:        1) the shroud support structure is fabricated                i from Alloy 600 material and its susceptibility to IGSCC is expected to be lower than the Type 304 stainless steel material,                    '
: 2) the shroud support structure is we3ded in a non-crevice configuration further reducing susceptibility to IGSCC, and 3) in this region of the vessel, the applied stresses are relatively low, the reactor coolant is expected to cause less oxidation, and the fluence levels are significantly lower.
Therefore, the scope of welds included in the initial shroud inspection plan for Hope Creek include shroud circumferential l
welds H-3, H-4, H-5 and H-7.                                                        .
l                        EXTENT OF INSPECTION:
l                        The extent of inspecticn of each of these four welds is based on factors such as access =tility, susceptibility, inspection technique, inspection equipment, neutron exposure (fluence), and evaluation methods. The initial extent of planned inspections exceeds the minimum sound ligament approach, described in Section                  l 3.0 or BWRVIP-01. The extent of inspections has been developed l
considering inspection logistics and outage impact.
The inspection technique planned for the initial inspection is
!                        Ultrasonic Testing ('UT ) . This technique is intended to
!                          interrogate _the volume of the subject welds and associated heat i                          affected Zones for cracking initiating on the inside surface (ID) 1 l
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    ,          -Document Control Dack                                                LR-N970332 Attachment
(                4 and portions of the outside surface (OD). The evaluation of inspection results will be consistent with the technique used.                        l The extent of inspection of each circumferential weld will vary,                      :
l              depending on the specific weld characteristics (i.e.
accessibility, inspection technique, safety significance, fluence, loads, evaluation methodology, and inspection results).
The initial extent of inspections planned will be the accessible length in a 360 . segment of H-3, H-4, H-5 and H-7.
Weld Number                  Extent of Inspection-                                    ;
H-3                  Accessible  length    in a  360  segment                        !
H-4                  Accessible  length    in a  360' segment                        !
H-5                  Accessible  length    in a  360  segment H-7                  Accessible  length    in a  360  segment EVALUATION:                                                                            :
i The evaluation of the inspection results will be conducted                            '
following the guidelines of BWRVIP-01. A combination of fracture mechanics methodologies will be utilized. The methodologies
;              applied, based on neutron fluence, will be Load Limit, LEEM -                          i l              Linear Elastic Fracture Mechanics, and EPFM - Elastic-Plastic                          l Fracture Mechanics.
For welds- with exposures less than or equal to 3E20 n/cm 2 , the Load Limit methodology will be utilized.          For welds with exposure between 3E20 n/cm2 and 1E21 n/cm', the Load Limit and LEFM/EPFM will be utilized.
l REPAIR:                                                                                I Hope Creek does not anticipate the need for repairs during RFO7.                      1 Discussions are being conducted with vendors to have the                                '
appropriate contingencies in place if a repair were to be needed.
The BWRVIP is anticipating Revision 2 to the BWRVIP Core Shroud Repair Design Criteria (BWRVIP-02).      Due to the short time duration to RFO7, we anticipate that the contingency shroud l              repair plans will use Revision 1 of SWRVIP-02.                                          ;
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