ML20080N111

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Response to Jh Rodriguez,Public Advocate of Nj,First Set of Interrogatories & Request for Production of Documents Re Welding.Certificate of Svc Encl
ML20080N111
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/13/1984
From: Martin T
Public Service Enterprise Group
To:
Shared Package
ML20080N096 List:
References
ISSUANCES-OL, NUDOCS 8402220120
Download: ML20080N111 (33)
v • d • e


Text

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' UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of  :

Public Service Electric and  : Docket No. 50-354 OL Gas Company  :

(Hope Creek Generating Station)  :

APPLICANT'S RESPONSE TO PUBLIC ADVOCATE'S FIRST SET OF INTERROGATORIES AND REQUEST FOR PRODUCTION OF DOCUMENTS Pursuant to the rules of practice of the Nuclear Regulatory Commission ("NRC"),10 C.F.R Section 2.740(b), and the Order of the Atomic Safety and Licensing Board of December 21, 1983 and the special prehearing conference of November 22, 1983, App!! cant, Public Service Electric and Gas Company ("PSE&G") hereby responds to the interrogatories and requests for production of documents propounded by the Public Advocate of New Jersey, Josenh H. Rodriguez.

Two matters require discussion. Several documents listed herein are proprietary and protected pursuant to 10 CFR 2.790 of the Commission's Regulations. If the intervenors desire to review these documents, it will be necessary to enter into an appropriate protective agreement with the designated company.

Second, the scope of the request for documents, eg.,

"all... reports... associated with... welding of piping at Hope Creek," involve numerous documents precluding any attempt at listing.

8402220120 840214 PDR ADOCK 05000354 o PDR

These documents will be made available for inspection by the intervenors at the Hope Creek Site if necessary.

Contention 1: Pipe Cracks

1. Specify each section of the Hope Creek Final Safety Analysis Report ("FSAR"), including Applicant's response to staff questions, and any amendments or updates thereof which Applicants assert are applicable to the consideration of the Public Advocate's Contention.

RESPONSE

Those sectione of the Hope Creek FSAR, including Applicant's response to staff questions, applicable to the Public Advocate's contention are as follows:

FSAR FSAR Section Amendment No.

1.) Table 1.3 Significant Design Changes from 0 PSAR to FSAR 2.) 1.8.1.31 - Conformance to RG 1.31 0 3.) 1.8.1.36 - Conformance to RG 1.36 0 4.) 1.8.1.37 - Conformance to RG 1.37 0 5.) 1.8.1.38 - Conformance to RG 1.38 0 6.) 1.8.1.39 - Conformance to RG 1.39 0 7.) 1.8.1.44 - Conformance to RG 1.44 0 l i

8.) 1.12.1 - Unresolved Generic Safety Issues 0 9.) 1.14.1.86 - Generic Licensing Issues -

Stress Corrosion Cracking of Stainless Steel 1 1

10.) 5.2.3.2.2 - BWR Chemistry of Reactor Coolant 0 l

1 u

s 3

11.) 5.2.3.4.1 - Avoidance of Stress Corrosion Cracking 0 l 12.) 5.2.3.5.1.2 - SRP Rule Review 0 a

13.) QR 250.2 2 14.) QR 281.10 2 15.) QR 281.12 2 1

2. Identify and specify all meetings, conferences, studies, reports, or other documentation relied upon by Applicants in considering the i

] problem of intergranular stress corrosion cracking ("IGSCC"). Provide copies of all such materials together with transcipts, minutes or notes taken during any meeting, proceedings, or other discussions related to the Applicant's response to the phenomenon of IGSCC.

l- RESPONSE Submitted herewith are listings of meetings, conferences and studies and indices of other documentation relied upon by Applicant in i

considering the problem of intergranular stress corrosion cracking. Applicant will mske copies of the documents available for review and reproduction in accordance with the Commission's regulations at the office of Richard Fryling, Jr., Associate General Solicitor, Public Service Electric and Gas Company, 30 Park Plaza - T5E, Newark, New Jersey 07101. In as much as the search for further documentation is continuing, the response to this interrogatory and document production request may be cupplemented if necessary.

3. Identify all persons, of ficials, or consultants now or formerly
employed by PSE&G to advise the Applicants ca) the phenomenon is IGSCC.

1 4

Provide copies of any reports, studies, or correspondence wherein these persons describe, analyze, or offer recommendations upon IGSCC.

RESPONSE

The persons named below have been involved with the issue of IGSCC on the Hope Creek Project:

PSE&G EMPLOYEES P. Landrieu W. Galley G. 3. Schnabel

3. E. Rogozenski R. F. Brandt D. Sachs R. Dunn GENERAL ELECTRIC EMPLOYEES
3. P. Higgins
3. Atwell
3. P. Clark R.' A. Proebstle S. Ranganath
3. N. Kass H. H. Klepfer G. M. Gordon E. Kiss BECHTEL POWER CORPORATION EMPLOYEES B. HacF.ney R. C. Bertossa W. R. Smith H. L. Leichter D. S. Kerr F. Breismeister See Answer to Interrogatory 2 on Contention 1.
4. Specify and describe in detail any mitigation measures, plans, or programs developed or under consideration by the Applicants for the prevention and/or mitigation of IGSCC.

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RESPONSE

See Answer to Interrogatory 2 on Contention 1; particularly Folder 1, Items 4, 8, and 10; Folder 2, Items 11,13,14, and 15; Folder 3, Item 3.

5. Identify any experts, employees, or consultants of the Applicants that have advised.or in the future will advise the company on IGSCC, and/or will testify for the Applicants in hearings on this contention.

Provide copies of their resumes and work product.

RESPONSE

See Answer to Interrogatory 3 on Contention 1. Applicant will identify prospective witnesses if other than those listed and resumes of prospective witnesses will be provided.

6. Identify and describe any and all "non-conformance reports"

("NR"), surveillance reports ("SR"), or other reports provided by contractors, subcontractors, inspectors, or other personnel associated with the purchase, '

delivery, installation and welding of piping at Hope Creek.

RESPONSE

Submitted herewith are indices of Nonconformance Reports, Quality Control Inspection Records, Quality Surveillance Reports and Quality Assurance Surveillance and Audit Activities associated with the Recirculation Piping and connections thereto related to Contention 1. Also included with the indices are lists of personnel involved with inspection, surveillance,

monitoring and audit activities. Applicant will make copies of the documents available for review and reproduction in accordance with the Commission's Regulations at the office of Richard Fryling, Jr., Associate General Solicitor, Public Service Electric and Gas Company, 80 Park Plaza - T5E, Newark, New Jersey 07101 and at the Hope Creek site as appropriate. See also Answer to Interrogatory 2 on Contention 1.

7. Identify all inspectors currently or formerly employed by the Applicants to examine Type 304 stainless steel piping or any other form of piping which carries coo! ant water.

RESPONSE

See Answer to Interrogatory 6 on Contention 1.

8. Identify the location of all NR's, SR's, or other inspection reports specified in Interrogatory 6, supra.

RESPONSE

See Answer to Interrogatory 6 on Contention 1.

Contention 2: Management Qualification

1. Provide a table of organization, showing the chain of communication and command, which the Applicants employ to manage the operation of nuclear plants.

RESPONSE

  • e

_7 The table of organization is included in Chapter 13 " Conduct of Operation" of the HCGS FSAR. Specifically, figures 13.1-1, 13.1-2, 13.1-6, 13.1-7, 13.1-8, 13.1-9, 13.1-10, 13.1-11, 13.1-12, and 13.1-13, detail the organization. Also, figure 17.2-1 in Chapter 17.2 " Quality Assurance During the Operations Phase" details the Manager - Quality Assurance Nuclear Operations organization.

2. Identify all persons, employees, officials, or consultc's currently or formerly employed by the Applicants who reviewed and/or participated in the Applicants' response to the ATWS incidents at the Salem Nuclear Generating Station in February,1983. Provide copies of all reports, studies, recommendations, correspondence or other material which sets forth their analysis and/or recommendations regarding the Salem ATWS.

l l

RESPONSE

The following personnel not including counsel were involved in the Reactor Trip Breaker Incident Response:

R.1. Smith R. MacWatters R. Skibinski R. M. Eckert V. Getzinger E. Renaud

! R. A. Uderitz R. E. Schaef fer R.A.B ke l R. A. Boettger E. S. Rosenfeld D. K. Hsu

3. M. Zupko R. A. Burricelli 3. C. Lai H.3. Midura H. D. Hanson B. E. Hall A. Nassman R. E. Gehret . P. Corletto D.3.Jagt S. LaBruna L. Leitz
3. D. Driscoll 3. Gallagher F. Sullivan j

E. A. Liden L. M. Fry L. Griffis P. M. Krishna L. K. Miller M. Morroni

- R. P. Douglas T. N. Taylor M. Shedlock R. L. Mitti L. A. Reiter R. Diaz R. D. Rippe R. Gura L. Santonastaso C. P. Johnson R. Stanley J. Fitzgerald I

R. S. Salvesen H. Baranek M. Allicock l F. Meyer R. P. Surman R. Settle W. L. Britz R. W. Beckwith R. Matts

3. A. Nichols D. Bhavani P. Mirchandani R. 3. DeSanctis L. Hajos 3. Quather E. Rozovski H.Lowe R. W. Hunsinger D. Namit D. Harding R. E. Tierney A. Sternberg M.Swann R. Namit W. Pavincich R. Franz O. Lee R. Bashall E. Crandall T. N. Cocco
3. Wroblewski L. Trow W. Nevins A. Gilrain . R. Oaks D. Perkins R. D'Orazio G. Kapp 3. Barger M. O. Banderia 3. Cortez DiCecca H. G. Berrick L. Catalfomo 3. M. DeStefano H. N. Trenka 3. Gueller 3. R. Franks A. P. Graham 3.Hagan 3. Gomeringer M. E. Gibbons 3. Jackson B. Leap .

M. R. Danak R. Newman B. K. Patrick i

3. C. Chamberlin R. VanderDecker 3. Lark
3. Owens B. Gadzinski A. Seibert
3. Wang N. Gerrity 3. Tully W. E. Reiber V. Polizzi S. Skabicki A. F. Fernandez A. Orticelli A. Darelius

, S. Makam D. E. Berry A. W. Robinson K. King R. Newman R. Jorgenson R. Minikel R. Frahm C. Kinsley K. Whitcomb M. Zeigler M. Rosenzweig W. Schultz W. Reuther Copies of reports, studies, recommendations and correspondence have been previously served upon the Department of the Public Advocate In the Matter of the Motion of Public Service Electric and Gas Company to reduce the Level of the Levelized Energy Adjustment Clause, before the State of New Jersey Board of Public Utilities, Docket No. 831-25 and are not being resubmitted herewith since they are in your possession and a e quite bulky and numerous.

In addition to the foregoing, the following will be made aval:able for review and reproduction in accordance with the Commission's Regulations at the office Richard Fryling, Jr., Associate General Solicitor,

., , . , ,_,-,-...,._,n.__ ,

4 Public Service Electric and Gas Company, 80 Pazk Plaza - T5E, Newark, New Jersey 07101.

1. Nuclear Oversight Committee Quarterly Report submitted to the NRC by letter of January 26,1984.
2. Letter to Eisenhut, re: Corrective Action Program, dated December 19,1983.
3. Nuclear Oversight Committee Charter submitted to the NRC by letter of December 8,1983.
4. Letter to Eisenhut, re: Corrective Action Program, dated Novamber 14,1983.
5. Supplemental Response to Generic Letter 83-28, dated November 7,1983.
6. PSE&G Action Plan dated August 26,1983.
7. BETA Corporation Reports submitted to the NRC by letter dated April 27,1983.
8. Management Analysis Company Report submitted to the NRC by letter dated June 29,1983.
9. Management Analysis Company Report (QA) submitted to the NRC by letter dated July 29,1983.
3. Identify and describe the Applicant's program for management of the operation and maintenance of the Hope Creek Nuclear Generating Station. Include the names and qualifications of a!! personnel in a management capacity and with authority to operate or oversee the operation of the Hope Creek Generating Station.

\

RESPONSE

Chapter 13 " Conduct of Operation" of the HCGS FSAR describes the program for management of the operation and maintenance of HCGS. Chapter 13, table 13.1-1 and table 13.1-4 provides the resumes of personnel in a management capacity and with authority to operate or oversee the operation of the HCGS.

4. Describe any and all operationni and/or management changes instituted by the Ap;T. cants at the Salem Generating Station following the ATWS of February,1983. Identify and describe any way in which these changes will be applied to Hope Creek.

RESPONSE

The Maintenance Department made changes to their Department Procedures and recommended changes to the Administrative Procedures.

The rewriting of these procedures incorporated materials given in Westinghouse Information Bulletins and incorporated more quality assurance involvement. The new procedures defined Post Maintenance Testing in greater detail. There have been increased manpower requirements and staffing levels in the Nuclear Operations Quality Assurance Department. The initiation of more intense training for Supervisors created four (4) new supervisor positions, which help support work load during training periods. A Computer Work Order Tracking System was developed with cooperation of Operations Department and I&C Department. Indirectly related to the ATWS incident, the Maintenance Department added a Licensed Operator position to their staff of supervisory personnel.

The"I&C Department made changes to their Department Procedures and recommended changes to the Administrative Procedures. The changes to the procedures also incorporated Westinghouse Information Bulletin material and developed clarification of testing and re-testing of components in procedures.

The I&C Department worked with Maintenance and Operations Department in developing Work Order Tracking Systems, which clearly defines testing and retesting procedures. In supervision, a licensed operator was added to the staff and the addition of another position for a supervisor is in the making.

The Chemistry Department made changes to their Department Procedures and recommended changes to the Administrative Procedures incorporating Westinghouse Information Bulletins. They also upgraded Supervisor Training, Work Order Tracking System and added a Licensed Operator to the Department Staff Personnel.

The Operations Department made changes to Department Procedures and recommended changes to Admin!strative Procedures in direct response to Emergency Instruction as per Reactor Trip Procedures. The Operations Department Directive ADi6 (Post Test Review) was developed as a direct result of the ATWS incident. They also were involved in the upgrading of the Work Order Tracking System.

Training for the Operations Department personnel has been increased as to ATWS. The department also assigned a specific supervisor to develop and follow the Work Order Retesting Program.

The plant has increased manning levels from 490 personnel to 558. In the Education Text TSSP (Technical Supervisory Skills Program)

, . ,-.m- - - , , . - . . - .,

1 training has been incorporated for all PSE&G Supervision. A PSE&G Action Plan was developed and initiated. The Nuclear Oversight Committee was i

formed and the Managed Maintenance Program was initiated involving the 1&C Department and Maintenance Department. The General Manager - Salem Operations and the General Manager - Nuclear Services exchanged positions, duties and responsibilities.

While these Salem specific improvements will not be directly applied to Hope Creek, industry i ecommendations such as INPO, Good Practices, and NRC Requirements and Guidelines, many of which have been promulgated as a result of the February 19,1983 ATWS events, are taken into consideration in the development of Hope Creek management and operational philosophies.

References to the foregoing have been previously served upon the Department of the Public Advocate as indicated in Answer to Interrogatory 2 on Contention 2 and likewise are not being submitted herewith, f Contention 3: Environmental Qualification 1.- Specify all sections of the Applicant's FSAR and any response to staff requests for information which the Applicants assert provide adequate information for the NRC to determine that safety related electrical and mechanical equipment are environmentally qualified at the Hope Creek Station.

RESPONSE

Those sections of the Hope Creek FSAR, including responses to staff requests for information, providing information on the environmental qualification of equipment are as follows:

j 1

FSAR FSAR Section Amendment No.

1.) Table 1.3 Significant Design Changes from 0 PSAR to FSAR 2.) 1.8.1.40 - Conformance to RG 1.40 0 3.) 1.8.1.63 - Conformance to RG 1.63 4 4.) 1.8.1.73 - Conformance to RG 1.73 0 5.) 1.E.1.89 - Conformance to RG 1.89 0 6.) 1.8.1.131 - Conformance to RG 1.131 4 7.) Table 1.11 Summary of Differences from SRP 4 8.) 1.12.1 - Unresolved Generic Safety Issues 0 9.) 1.14.1.67 - Generic Licensing issues - Harsh Environment for Electrical Equipment Following i HELB 10.) 1.14.1.77 - Generic Licensing Issues - Protection of 2 Equipment in MS Pipe Tunnel 11.) 1.14.1.121 - Generic Licensing Issues - Environmental 1 Qualification of Equipment 12.) 3.1.2.1.1 - Conformance to GDC 1 0 13.) 3.1.2.1.2 - Conformance to GDC 2 0 14.) 3.1.2.1.4 - Conformance to GDC 4 . 0 15.) 3.1.2.1.23 - Conformance to GDC 23 0 16.) 3.6.1 - Postulated Piping Failures in Fluid Systems 0 17.) 3.11 - Environmental Design of Mechanical and 0,1,2,0 Electrical Equipment 18.) 7.1.2.2 - Conformance to GDC's 0 19.) 7.1.2.3 - Conformance to IEEE Standards 0 20.) 7.1.2.4 - Conformance to Regulatory Guides 0

FSAR FSAR Section Amendment No.

21.) QR 270.1 4 22.) QR 270.2 2 23.) QR 271.4 4 24.) QR 430.35 4 25.) QR 430.31 4 26.) QR 430.54 4 27.) QR 430.55 4 28.) QR 430.39 4 29.) QR 440.7 2 30.) SRAI (3) 4

2. Identify any and all persons, of ficials, employees or consultants with responsibility, currently or formerly for the Applicant's program of environmentally qualifying safety related electrical and mechanical equipment.

RESPONSE

The following is a list of personnel who have been involved in the Hope Creek Environmental Qualification Program:

PSE&G P. Landrieu W. Galley R. Salveson F. A. Christiana

3. J. Wroblewski W. M. Pavincich R. D'Orazio T. Narang P. D. Thompson R. Drewnowski H. W. Peterson R. V. Snow R. Bashall

Prot > Power M. Annon C. Hallahan G. Geany

3. Lariveire R. Frantz E. Crandal D. Harding Bechtel G. Kapandritis '

i R. Dusterdick M. Baxi R. Goel F. Borgman I. Sturman General Electric N. G. Lurie

3. 3. Jolly R. W. Friis

. H. P. Williams L. D. Test

. R. F. McClelland  ;

~

F. E. Hatch C. W. Dillmann t D. W. Reigel P. R. Scherer W. M. Davis

3. Identify any and all reports, studies which the Applicants assert show the environmental qualification of safety related electrical and I mechanical equipment at Hope Creek. In particular, identify all reports, including NR's, SR's, and other documentation in the possession of the Applicants which relate to environmental qualification.

RESPONSE

Listed below are indices of documentation (a) programmatic in nature (b) related to electrical equipment and (c) related to mechanical equipment concerning the environmental qualification of safety related electrical and mechanical equipment as set forth in Contention 3. See Answer to Interrogatory 2 on Contention 1. Applicant will make copies of the documents available for review and reproduction in accordance with the

Commission's regulations at the office of Richard Fryling, Jr., Associate General Solicitor, Public Service Electric and Gas Company, 80 Park Plaza -

T5E, Newark, New Jersey 07101.

3(a) Following is the index of documentation programmatic in nature supporting the Hope Creek Environmental Qualification Program:

1) " General Electric Environmental Qualification Program" NEDE-24326-1-P Licensing Topical Report (Proprietary)
2) " General Electric Environmental Qualification Program" Scope of Work for Phase 1 (Proprietary)
3) " General Electric Environmental Qualification Program" Scope of Work for Phase 2 (Proprietary)
4) " General Electric Environmental Qualification Program" Scope of Work for Phase 3 (Proprietary)
5) " General Project Requirement Environmental Qualification of Safety Related Equipment" 10855-G-013(Q)

(Non-Proprietary)

6) " Environmental Design Criteria for the Hope Creek Generating Station" 10855-D7.5 (Non-Proprietary)

d 3(b) The following reports show environmental qualification of safety related electric equipment for Hox Creek Generating Station:

1) " Qualification for Westingbouse Class IE Motors" Doc. I.D. - DO-146F (Proprietary)
2) " Qualification Tests of Solenoid Valves..." Test Report No. AQS21678/TR - Rev. A (Proprietary)
3) "Special 600 Volt Sih!ded Instrument Cable" Report No. 558-1088 (Non-Proprietary)
4) "600 Volt Control Cable" Report No. HC 0579-1, Rev. 2 (Non-Proprietary)
5) "Raychem WCSF-N Splice Kit Tubing" Report No. PEN-TR-8172 (Non-Proprietar y)
6) "5KV Power Cable" Report No. HC 0579-3A, Rev.1 (Non-Proprietary)
7) " Indoor Metal Clad Switchgear" Report No. 33-52260-QS, Rev.2 (Proprietary)
8) " Westinghouse Model 32, Series 2 Qualifications Program" Report No. 5519A32 (Non-Proprietary)
9) "SMB-0-25 Valve Actuator" Report No. 600376A (Proprietary)
10) " Power Range Detector" Book #6 DRF #A00-01482 MPL #Bil-D193 (Proprietary) l
11) " Electrical Protection Assembly" Book #8 DRF #A00-01428 MPL #C71-5003 (Proprietary)
12) " Pressure Transmitter" Book #11 DRF #A00-01428 MPL #B21-N075, B21-N076, C71-N052 (Proprietary)
13) " Level Transmitter" Book #12 DRF #A00-01428 MPL #E11-N008 (Proprietary)
14) " Pressure Switch" Book #16 DRF #A00-01428 MPL #C71-N005 (Proprietary)
15) " Temperature Switch" Book #18 DRF #A00-01428 MPL #C41-N003 (Proprietary)
16) " Conductivity Cell" Book #21 DRF #A00-01428 MPL # Ell-N001 A, B (Proprietary) 3(c) The following reports show environmental qualification of safety related mechanical equipment for HCGS:

Date: Feb.,1984

1. Index
2. Report of Hope Creek Generating Station PSE&G/NRC Equipment Qualification Meeting of November 29,1983
3. Beciitel E002042 - Degradable Mechanical Parts Program January 18,1984 (Review of "Q" harsh environment purchase orders for non-metallic companents as phase 1 of the degradable components review task.)
4. General Electric GP-83-195 Hope Creek Project Non-metallic material lists for Hope Creek Mechanica!

Equipment Environmental Qualification Program December 29,1983 (completed under Work Authorization No. 7, 20 dated l

October 21,1983) l l

5. Mechanical Equipment
4. loentify and describe any studies, reports, or other documentation prepared by persons or agencies not under the control or l direction of the Applicants, which the Applicants have used or relied upon in

! qualifying safety related electrical and mechanical equipment.

RESPONSE

i The documents listed below represent the primary sources of I regulatory requirements that the Hope Creek Environmental Qualification l

program is based upon. Secondary documentt, that are referenced by these primary documents are not included.* Conformance to any particular NRC ,

Regulatory Guide can be found in Section 1.8 of HCGS FSAR.

FEDERAL REGULATIONS 10 CFR 50.49 10 CFR 50, Appendix A, GDC 4 l l

NRC REGULATORY GUIDES R.G.1.75 R.G.1.97 R.G.1.89 NUREG DOCUMENTS l NUREG-0588 NUREG-0800, Section 3.11 INSTITUTE OF ELECTRICAL AND ELECTRONIC ENGINEERS STANDARDS IEEE 323-1974 l

i

  • Secondary standards are available in public libraries, technical societies, and public reading rooms.

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e STATE OF NEW JERSEY )

ss.

COUNTY OF ESSEX- )

Thomas 3. Martin, being first sworn, deposes and states:

That he is Vice President, Engineering and Construction of Public Service Electric and Gas Company, the Applicant herein; that he has read the foregoing Applicant's Response to Public Advocate's First Set of Interrogatoriu and Request for Production of Documents, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

AbW Th6 mas J tin Vice Pre ent Subscribed and sworn to before me this/3 ay of February 1984.

Ml YLLl4 '

i10SANN Del TUFO Dil0d

  • 0'ARY PUBLIC OF NEW JERSEY My Commission Expires April 18,1984

PUBLIC ADVOCATE (PA) CONTENTION 1: PIPE CRACKS Articles 2, 3, and 4 (PA-1 art. 2 thru * )

TABLE OF CONTENTS Folder 1

1. General Electric (G.E.) letter to Public Service Electric and Gas (PSE&G) dated 6/27/75 (GP-75-86 ) -

" Removal of Recirculation Four-Inch Bypass Line".

(PA-1 art. 2, 3, & 4)

2. G.E. letter to Bechtel Power Corporation (Bechtel) dated '

1/7/76 (GB 4 ) -

"G.E. Implementation Plan For Stainless Steel Pipe Fixes".' (PA-1 art. 2, 3, & 4)

3. PSE&G Meeting Notes dated 8/2/76 -

" Material Degradation in BWR Plants" (with attachments) .

(PA-1 art 2)

4. G.E. letter to Bechtel dated 1/13/78 (GB78-18) -

" Hope Creek Project Intergranular Stress Corrosion

,! Cracking (IGSCC) Prevention For External Jet Pump Riser Piping". (PA-1 art. 2, 3, & 4)

5. PSE&G Meeting Notes dated 3/7/78 -

" Field Welding of NSSS Piping" (with attachments) .

l l (PA-1 art. 2, 3, & 4)

6. PSE&G letter to Bechtel dated 3/28/78 (PLB-2850) -

" Recirculation Line Bypass Modification" ,

(

l (with attachments) . PA-1 art. 3 & 4)

PSE&G letter to Bechtel dated 4/20/78 (PLB-2 89 3) -

" Field Welding of G.E. NSSS Piping". (PA-1 art. 3 & 4) 7.

l

8. G.E. letter to Bechtel dated 7/24/78 (GB- 7 8-15 8 ) -

"IGSCC Countermeasures for the Hope Creek Recirculation System" . (witn attachments) . (PA-1 art. 2, 3& 4) 9.

PSE&G Internal Memo, Chief Mechanical Engineer (CME) to General Manager Engineering (G.M. - Engg.) dated 1/25/79 -

" Recirculation Piping Hope Creek Generating Station"

.(with attachments) . (PA-1 art. 3& 4)

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_ . _ _ . _ _ _ _ . . _ . _. ~ _ . . _ _ _ _ _ _ _ _ . _

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TABLE OF CONTENTS Folder 1 10.

t Bechtel letter to G.E. dated 5/15/79 (BLG-938) -

" Recirculation Piping - Mitigation of IGSCC" i

(with attachments) . (PA-1 art. 3 & 4) 11.

Bechtel letter to PSE&G dated 8/29/79 (BLP-8566) -

" Recirculation System, Corrosion Resistant Cladding (CRC) ~and Solution Heat Treatment (SHT) , G.E. Quotation".

(PA-1 art. 3& 4)

12.

! dechtel letter to G.E.

" Recirculation Piping dated 9/6/79 (BLG-1024) -

Shipment". (PA-1 art 3) 13.

PSE&G Internal Memo, CME to G.M. - Engg. , dated 9/19/79 -

" Recirculation Piping Recommendation for Approval of )

Funds". (PA-1 art. 3& 4) I

14. I PSE&G letter to Bechtel dated 9/25/79 (PLB-3630) -  !

" Recirculation Piping System CRC and SHT Approval of 1 Costs". (PA-1 art. 3& 4)

15. G.E. Specification P50YP175 dated February 1978 -

" Corrosion Resistant Weld Deposition Requirements for  !

Austenitic Stainless Steel Piping". (PA-1 art. 2& 4) '

16.

PSE&G Internal Memo, Principal Engineer to CME, dated 3/8/82 -

" Recirculation Piping Shop Work" (with attachments) .

PA-1 art. 3 & 4) 1

17. Associated Piping and Engineering (APE) letter to G.E.

dated.3/28/83 -

" Weld Repairs to Original Pipe Spool Welds After SHT Operations" (with attachments) . (PA-1 art. 2, 3& 4) 18.

PSE&G Internal Memo, Principal Engineer to CME, dated 5/19/83 -

" Recirculation Piping IGSCC Mitigation, Shop Work".

(PA-1 art. 3& 4) 19.

PSE&G Internal Memo, Principal Engineer to CME, dated 5/26/83

" Recirculation Piping IGSCC Mitigation, Shop Work". ,

(PA-1 art. 3& 4) l 20. G.E.

letter to Bechtel dated 5/26/83 (GB-83-95) -

" Recirculation Piping Defects Discovered at Supplier's l

Shop". (PA-1 art. 3& 4) i-

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TABLE OF CONTENTS Folder 1

21. PSE&G Internal Meno, Principal Engineer to CME, dated 6/10/83 -

" Recirculation Piping Examination". (PA-1 art. 3& 4)

22. PSE&G Internal Memo, Principal Engineer to CME, dated 8/14/83 -

" Recirculation Piping Testing". (PA-1 art. 3& 4)

23. G.E. letter to Bechtel dated 10/12/83 -

" Recirculation Piping Defects Discovered at Supplier's 3 & 4) '-

Shop" . (with attachment) . (PA-1 art. 2,

24. PSE&G Internal Memo, Chief Project Engineer to Manager -

Quality Assurance, dated 1/26/84 -

" Recirculation Piping Defects Discovered at Supplier's ,

Shop" (with attachment) . (PA-1 art. 2, 3& 4) _ ['

a TABLE OF CONTENTS FOLDER 2

1) NRC letter to PSE&G, dated February 17, 1978 "NRC Staff Position on the use of Austenitic Stainless Steel in BWR's - Hope Creek Generating Station" with NUREG-0313 " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping" (PA-1 Art. 2 and 4)
2) Bechtel letter to PSE&G dated March 7, 1978, (BLP-6528),

"NRC staff Position on the use of Austenitic Stainless Steel" (PA-1 Art. 3 and 4)

3) G.E. Letter to PSE&G, dated September 18, 1978, (GB-78-44)

" Hope Creek Project IGSCC" with "G.E. Meeting Minutes with NRC" dated September 12, 1978. (PA-1 Art. 2& d)

4) PSE&G letter to NRC, dated April 13, 1979,

" Schedule for Response to NRC Staff Position on the use of Austenitic Stainless Steel in BWR Facilities" (PA-1 Art. 3)

5) Bechtel letter to PSE&G, dated September 4, 1979, (BLP-8599)

"NRC Staff Position on the use of Austenitic Stainless Steel (NUREG-0313)" with attachment. (PA-1 Art. 3 and 4)

6) PSE&G letter to NRC, dated September 28, 1979,

" Response to NRC Staff Position on the use of Austenitic Stainless Steel in BWR Facilities" with attachment (PA-1 Art. 3 and 4 )

7) Office of Nuclear Reactor Regulation, NUREG-0313, Rev. 1, Published August, 1980, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping" (PA-1 Art. 2 and 4)
8) NRC -; o to all BWR Licensees , dated February 28, 1981,

" 1.m ; ' c..e n t a t i o n o f NUREG-0313-Rev. 1" (PA-1 Art. 2 and 4)

9) PSEIC _etter to Bechtel, dated April 30, 1981, (PLB-4369),

"N.:.C .: aff Position on the use of Austenitic Stainless Stes. n BWR Facilities, NUREG-0313, Rev. 1" with attach-me:n . FA-1 Art. 2 and 4)

10) Be r. letter to PSE&G, dated June 22, 1981, (BLP-10,979)

" N.t . .sition on the use of Austenitic Stainless Steel in Bhl rilities, NUREG-0313, Rev. 1" with attachment, IFA . Art. 3 and 4)

. . . s

'I- PSE&G 1etter to NRC, dated July 7, 1981, "Responss to Imp;cmentation of NUREG-0313, Rev. 1" with attachment. (PA-1 Art. 3 and 4 )

12) NRC IE Bulletin 83-02: Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BWR Plants" dated March 4, 1983.
13) KMC Inc. letter to PSE&G dated July 19, 1983,

" Report of NRC Meetir.gs on Cracks in Large Diameter Pipes" with attachment (PA-1 Art. 2)

14) EPRI letter to BWR Owners Group Members dated December 12, 1983,

" Procedural Guidance for Pipe Replacement at BWRs" with attachment. (PA-1 Art. 2)

15) KMC Inc. letter to PSE&G, dated November 15, 1983,

" Report of NRC and EPRI Presentations on Status of Cracks in BWR Piping" with attachment. (PA-1 Art. 2) 4

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i PUBLIC ADVOCATE (PA) CONTENTION 1: PIPE CRACKS i TABLE OF CONTENTS Folder 3 l

1. Nuclear Safety, Volumn 17, July -- August 1976 -  :

" Pipe Cracks in BWR".

t

2. G.E., " Evaluation of Near-Term BWR Piping Remedies",

i dated 10/20/78, with attachments. (PA-1 art. 2)

3. EPRI Journal, December 1982 -

" Mitigation of IGSCC in BWR Stainless Steel Piping".

(PA-1 art.2) 4.

' EPRI First Use Report, "BWR Piping: Induction Heating to Prevent Cracking". (PA-1 art. 2) 5.

EPRI First Use Report, " Radiographic Inspection Using MINhC (SHRINKAC) " . (PA-1 art. 2) i

6. G.E. BWR Technology . Report, " Hydrogen Water Chemestry" (PA-1 art. 2) and others , including the following listed EPRI Reports which are available for review at ER R po t Nos RP-WS79-174 vol. 1-4 RP-Tll5-03  !

RP-T101-05 RP-T118-13 .-

RP-0700-06 RP-T115-02 ,

RP1332-02 RP-T118-04 '

RP-T115-01 RP-T115-04 RP-T114-02 RP-T302-02 RP-T106-02 ,

RP2405-02 RP-Til8-06 "

RP-T106-01 RP-T109-01 f

RP-T114-10 BWROG; GPU 188.312.1 ,

RP0603-03 RP-T118-02 BWROG; NMPC GN407 RP-T118-01 RP2058-06 BWROG; L.I.C.-81-412 RP2057-03 RP1563-01 BWROG; CPLC RP1930-04 RP-T113-04 RP-T104-01 RP-Tll3-01 RP-T103-04 RP-T101-02 RP1325-03 RP1167-08 RP-T115-06 RP0607-02 RP-TPS75-603 RP-T118-12 RP-Till-01 RP-T109-04 RP-T113-06 RP-T109-03 RP-T116-01 l

RP1562-02 RP1071-01 RP-Til8-ll RP-T109-02 l

RP-T104-02 RP1070-01 RP-T119-01 RP0311-03 RP2006-04 RP-Til8-08 RP-Til7-02 RP-T113-05 RP-Til7-01

4

  • e RECIRCULATION PIPING REFERENCES J. M. Skarpelos and J. W. Bagg, Chloride Control in BWR Coolants, NEDO-10899, General Electric, June 1973.

W. L. Williams, Corrosion, Vol 13, p. 539t, 1957.

M. B. Reynolds, Failure Behavior in ASTM A106B Pipes Containing Axial Through-Wall Flows, GEAP-5620, April 1968.

Investigation and Evaluation of Cracking in Austenitic Stainless Steel Picinq of Boiling Water Reactor Plants, NUREG 76/067/NRC/PCSG, October 1975.

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4 RECIRCULATION PIPING

! INDEX I. Nonconformance Reports 202 999 1080 2565 1104 1131 2691 2927 II. Quality Control Inspection Records By Log Number i (connection to other systems)

P-5262 W-14559 W-16918 W-17403 III. Quality Control Personnel Who Performed Inspection Activities 4

s IV. Quality Control Inspection Records By Log Number (for installation of RECIRC Piping)

P-354 P-380 ._ W-3653 W-1467 W-1536 P-2328 W-1546 W-1537 W-5490 W-1623 W-1677 W-5491 P-355 P-381 P-2329 W-1468 W-14051 W-5492 P-364 W-15016 W-5493 W-1513 W-16209 W-5866 W-1512 W-1539 W-6198 P-365 W-16361 P-2691 W-1514 W-1538 W-7435 W-1544 W-1815 W-6460 P-366 P-382 W-6459 W-1515 W-1540 W-9424 W-1828 W-1779 P-2773 W-1516 W-1541 W-6576 P-367 W-1713 W-6577 W-1517 P-1524 W-7193 P-379 W-3650 U-7772 W-13688 W-3797 W-8602 W-14749 W-3651 W-10327 W-1535 P-1525 P-3105 W-1534 W-3652 W-7444

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IV. cont.

W-7445 P-3174 -

W-7650 W-7649 P-3749 W-9156 W-9157 P-3849 W-9425 W-10326 W-10803 W-9426 W-10(*27 W-11765 W-13884 W-14021 V. Quality Control Inspection Records Ly Log No.

(for Receiving Inspection)

Q-56 NSSS-382 (pg. 1) NSSS-480 Q-223 NSSS-285 NSSS-382 (pg. 2) Q-256 NSSS-212 Q-229 NSSS-417 NSSS-483 Q-224 NSSS-396 Q-254 Q-257 NSSS-279 NSSS-402 NSSS-353 Q-222 Q-227

', NSSS-362 (pg.1) NSSS-450 NSSS-203 NSSS-362 (pg. 2) Q-255 NSSS-206 VI. Procurement Supplier Quality Personnel Who Performed Surveillance Activities ,

VII. Quality Surveillance Reports QSR# QSR# QSR#

1 16 30 2 17 31 3 18 32 4 19 33 5 19-1 34 6 20 35 7 21 36 8 22 37 9 23 38 10 24 39 11 25 40 12 26 41 13 27 42 14 28 43 15 29 44 45

4

-. l VIII. Qualitv Assurance Surveillance and Audit Activities  ;

QA Work Plan and Log (three sheets)

QA Work Plan and Log for 2/16/82 to 2/28/82; W. Goebel, assigned QAE.

  • QA Work Plan and Log for 11/15/82 to 11/26/82; ~

A. Lance, assigned QAE.

QA Work Plan and Log for 11/29/82 to 12/10/82; W. Goebel, assigned QAE.

l QA Audit Report 24.1-5 and Audit Checklist Sheets No. 2,3,4,5,8,9, 10, 11, 14, 15 and 17. l QA Audit Report Report 13.1-9 and Audit Checklist Sheets No. 2, 3, 4, 5, 8 and attachment.

IX. Quality Assurance Engineers Who Performed Surveillance, Monitoring, I

or Audit Activities t

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i DOLY:Ti*

'n ?& L W FEB 16 A10:19 UNITED STATES OF AMERICA NUCLEAR REGULATORY COggggli,g DRANCW Before the Atomic Safety and LicensiniBoard Public Service Electric and )

Gas Company )

) Docket No. 50-354-OL (Hope Creek Generating )

Station) )

CERTIFICATE OF SERVICE I hereby- certify that copies of " Applicant's Response to Public Advocate's First Set of Interrogatories and Request For Production of Documents," dated February 14, 1984 in the captioned matter have been served upon the following by deposit in the United States mail on tnis 14th day of February,1984:

Marshall E. Miller, Esq. Atomic Safety and Chairman Licensing Appeal Panel Atomic Safety and U.S. Nuclear Regulatory Licer: sing Board Panel Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20535 Atomic Safety and Licensing Board Panel Dr. Peter A. Morris U.S. Nuclear Regulatory Atomic Safety and Commission Licensing Board Panel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Docketing and Service

- Washington, D.C. 20555 Section Office of the Secretary Dr. James H. Carpenter U.S. Nuclear Regulatory Atomic Safety and Commission Licensing Board Panel Washington, D.C. 20555 U. S. Nuclear Regulatory Commission Lee Scott Dewey, Esq.

Washington, D.C. 20555 Office c1 the Executive Legal Director Theodore C. Granger U.S. Nuclear Regulatory Deputy Public Advocate Commission Department of the Public Advocate Wasnington, D.C. 20555 Division of Rate Counsel 744 Broad Street 30th Floor Newark, New Jersey 07102

i. ,
  • A Troy B. Conner, Jr., Esq.

Conner and Wetterhahn 1747 Pennsylvania Avenue,N.W.

Washington, D.C. 20006 R. William Potter, Esq.

Susan C. Remis, Esq.

State of New Jersey Department of the Public Advocate CN 850 Hughe:, Justice Complex Trenton,New Jersey 08625 Carol Delaney, Esq.

Deputy Attorney General Department of Justice State Office Building 8th Floor

' 820 N. French Street Wilmington, DE 19810 A p/ t .

Richard >yli(g , Jr.

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