ML20079L983

Forwards Addl Info in Response to NRC Re Util Request for Authorization to Use Certain Components Designed to Codes & Stds for Coolant Pressure Boundary Equipment Specified in 10CFR50.55a,Subsections C-F

ML20079L983
Person / Time
Site:	Hope Creek
Issue date:	02/10/1983
From:	Mittl R Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8302230531
Download: ML20079L983 (15)

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O PSEG Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 February 10, 1983 Director of Nuclear Reactor Reguletion U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 CODES AND STANDARDS FOR REACTOR COOLANT PRESSURE BOUNDARY EQUIPMENT This letter is in response to NRC staff request, dated November 4, 1981, for further information relating to Public Service Electric and Gas Company's request for authorization to use certain components in its Hope Creek Generating Sta-tion Unit 1, which were designed to codes which differ from those specified in subsections (c) through (f) of 10CFR50.55a.

l Public Service Electric and Gas Company's initial request of January 30, 1979, provided a listing of the reactor coolant pressure boundary components for the Hope Creek Generating Station Unit 1, and indicated the purchase order date and the codes each component is constructed to. As requested by l the NRC staff, the attachment to this letter provides addi-tional information to indicate the codes which are permitted by 10CFR50.55a, and the results of our analysis which iden-l tifies and summarizes for each component the requirements contained in the codes permitted by 10CFR50.55a which are interpreted as being different than the requirements in the code edition and addenda used for construction of the com-ponents. As used in Attachment I, the term " Code of Con-struction" shall mean the code used in the constt3ction, and the term " Code of Comparison" shall mean the code edition and addenda of ASME Section III permitted by 10CFR50.55a.

I Code paragraph references and titles listed in Attachment I l are from the code edition and addenda of ASME Section III l permitted by 10CFR50.55a for each component.

8302230531 830210 DR ADOCK 05000354 PDR The Energy People 95 0342

Director of Nuclear 2/10/83 Reactor Regulation The design, fabrication, and testing of these components are in accordance with the recognized codes and standards in ef-fect at the time the components were ordered and provide an acceptable level of quality and safety. Public Service Electric and Gas Company believes that the revisions identi-fied to the " Code of Construction" do not increase the level of quality and safety to compensate for the severe hardship that would be encountered in meeting all requirements of the later codes.

We trust that this transmittal fulfills the NRC staf f 's re-quest for additional information on this matter and will en-able resolution of Public Service Electric and Gas Company's request for an authorization from the Commission in accord-ance with Section 50.55a(a) (2) (i) and (ii) of 10CFR Part 50 to use the codes referenced for the components listed in the attachment to this letter.

Very truly y urs, ll /$ I R. L. Mittl General Manager -

Nuclear Assurance and Regulation DJD:df Attachment CC: D. H. Wagner USNRC Licensing Project Manager Mr. W. H. Bateman USNRC Senior Resident Inspector BD25 1- 2

ATTACHMENT Page 1 of 13 A. Equipment: Reactor Pressure Vessel Purchase Order Date: May 7, 1970 Code of Construction: ASME III, 1968 Edition with Winter 1969 Addenda Code of Comparison: ASME III, 1971 Edition with Summer 1972 Addenda Analysis of Difference:

GENERAL REQUIREMENTS

a. Stress Reports: NA-3260 (a) - Incorporated addi-tional requirement for review of RPV manuf acturer's stress report.

b. Responsibilites for QA: NA-3361 (a) - Incorporated additonal requirement for RPV manuf acturer to survey and qualify his subcontractor 's QA program.

MATERIALS

c. Welding Material Identification: NB-2152 - Incorp-orated specific requirements to provide marking on packages and containers to insure positive ide nti-fication of the material.

d. Number of Impact Test Specimens: NB-2323 - In-creasec the number of tests for heavy plates from one to t. u. .

e. Fracture Toaghness Requirements: NB-2300 - Incorp-orates alternative test procedures for determining fracture toughness characteristics.

f. Bolting haterial Test Results: NB-2333 (2) - In-troduced Charpy V-notch test acceptance criteria in terms of mils lateral expansion in lieu of ft.-lb.

absorbed energy requirements,

g. Design Stress Intensity Values: - No change in design stress intensity values for RPV plate material.

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r-Page 2 of 13 DESIGN

h. Loading Criteria: NB-3114 - Clarifies that " Test-ing Conditions" are tests in addition to the ten (10) hydrostatic or pneumatic tests permitted by the Code, and requires that stress analysis cover the hydrostatic testing load condition.

i. Protection Against Nonductile Fracture: NB-3 211 (d )

- Incorporates additional requirenent to provide protection against nonductile fracture,

j. Thermal Stress Ratchet: NB-3222.5 - Provided a new approach to analyzing and evaluating stress.

k. Design Methods: - Incorporates revised design and analysis requirements.

FABRICATION AND INSTALLATION _

l. Procedure Qualification Test: NB-4213.2 - Incorp-orates a comprehensive and detailed procedure for these tests.

m. Qualification Requirements for Welding Specially Designed Welded Seal: NB-4360(a) - Incorporates new welding procedure not previously covered.

EXAMINATION

n. Examination of Specially Designed Welded Seals:

NB-5370 - Incorporates examination requirements for welding procedure not previously covered.

o. Examination After Hydrostatic Test: NB-5410 -

Incorporates new requirenent to examine, by magnetic particle or liquid penetrant methods, welds subsequent to hydrostatic or pneumatic tests.

TESTING

p. Testing of Specially Designed Welded Seals: NB-6127

- Incorporates testing requirements for welding procedure not previously covered.

B. Equipment : Control Rod Drive Housings Purchase Order Date: January 5, 1971 l Code of Construction: ASME III, 1968 Edition with Summer 1970 Addenda

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Page 3 of 13 Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda Analysis of Dif ference:

General Requirements

a. Stress Reports - See Reactor Pressure Vessel b Responsibilities for QA - See Reactor Pressure Vessel Materials

c. Welding Material Identification - See Reactor Pres-sure Vessel

d. Design Stress Intensity Values - Stress Intensity Values were increased 0.8 Ksi at 600F for the flange and 0.9 ksi at 600F for the cape materials.

Design

e. Loading Criteria - See Reactor Pressure Vessel

f. Design Methods - See Reactor Pressure Vessel.

C. Equipment : Control Rod Drive Purchase Order Date: August 18, 1971 Code of Construction: ASME III, 1968 Edition with Winter 1970 Addendum.

Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda.

Analysis of Dif ference: Code of Comparison as outlined for the CRD Housings is appli-cable to the CRD, except that t

design stress intensity values j for the CRD material did not l change.

D. Equipment: Power Range Monitor Incore Housings l

Purchase Order Date: January 5, 1971 j Code of Construction: ASME III, 1968 Edition with Summer 1970 Addenda, t

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L Page 4 of 13 Code of Comparison: ASME III, 1971 Edition with . Winter 1972 Addenda.

Analysis of Dif ference: Code of Comparison as outlined for the CRD Housings is appli-cable to the Power Range Moni-tor Incore Housing.

E. Equipment: Jet Pump Instrumentation Penetration Purchase Order Date: January 5, 1971 Code of Construction: ASME III, 1968 Edition with Summer 1970 Addenda.

Code of Comparison: ASME III, 1971 Pdition with Winter 1972 Addenda.

Analysis of Difference: Code of Comparison as outlined for the CRD Housings is appli-cable to the (JPIP).

F. Equipment: Main Steam Line Safety Relief Valves Purchase Order Date: January 28, 1971 Code of Construction: Nuclear-Pump and Valve Code, 1968 Edition with 1970 Addenda.

Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda.

Analysis of Difference:

General Requirements

a. Stress Reports - See Reactor Pressure Vessel

b. Manufacturer's Responsibilities: NA-3320 - Up-graded requirements for having a documented QA pro-gram and for qualification of material manufacturer's QA programs.

c. Quality Assurance: NA-4100 - Sets forth require-ments for planning , managing , and conducting QA programs and the rules governing the evaluation of such program prior to issuance of Certificate of Authorization for the manuf acture and installation of Class 1, 2, and MC components .

d. N-Type Symbol Stamp: NA-8220 - Incorporates requirement for the N-Type Synbol Stamp.

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g Page 5 of 13 Materials

a. Heat Treatment of Test Coupons: NB-2211 - Incorp-orates guidelines for heat treatment of test speci-mens, not previously covered.

b. Impact Testing Requirements: NB-2300 - Sets forth requirement for impact testing of ' Class 1 com-ponets, previously established as optional.

c. Impact Testing - Number of Tests and Locations:

NB-2332 - Sets forth requirement for impact testing of pressure retaining materials with nominal thick-ness 2-1/2 inch and less, previously established as optional.

d. Bolting Materials - Charpy V-Notch Testing:

NB-2333(2) - Incorporates additional require ment for Charpy V-Notch testing bolting materials, not previously required.

e. Documentation and Maintenance of QA Program:

NB-2610 - Establishes documentation and qualifica-tion requirements for the QA program of the mate-rial manuf acturer, not previously required,

f. Design Stress Intensity Values - No change in design stress intensity values for valve body material.

Design

a. Standard and Alternate Design Rules: NB-3512.1 and

.2 - Incorporates additional acceptance criteria for minimum valve body thickness, in lieu of the criteria contained in USAS B16.5.

b. Prevention of Nonductile Failure: NB-3 511 -

Incorporates additional requirements for prevention of nonductile failure, not previously established.

Fabrication and Installation

a. Impact Tests: NB-4121.2 - Incorporates additional requirements for the repeat of tensile and impact tests, not previously covered.

b. Qualification of Forming and Bending Process:

NB-4213 - Incorporates requirement for procedure ,

qualification tests to determine impact properties )

after straining, not previously covered.

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c. Impact Tests of Weld Deposits: NB-4335.1 - Incorp-orates requirement for impact tests of welding deposit for welding - procedures qualification not previously covered.

d. Time Temperature Recordings: NB-4 632. 2 - Incorpor-ates requirement for a time-temperature recording of all postweld heat treatments, not previously covered.

Testing

a. Hydrostatic Testing: NB-6111(b) - Introduces requirement that hydrostatic testing of subject components be witneelnd by the Authorized I ns pe ctor .

G. Equipment: Main Steam Line Isolation Valves Purchase Order Date: October 8, 1969 Code of Construction: Nuclear Pump and Valve Code, 1968 Edition .

Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda.

Analysis of Difference:

General Requirements

a. Stress Reports - See Reactor Pressure Vessel

b. Manufacturer's Responsibilities: See Main Steam Line Safety Relief Valves.

c. Quality Assurance: See Main Steam Line Safety Relief Valves.

d. N-Type Symbol Stamp: See Main Steam Line Safety Relief Valves. 4 Materials

a. Heat Treatment of Test Coupons - See Main Steam Line Safety Relief Valves.

b. Impact Testing Requirements - See Main Steam Line Safety Relief Valves.

c. Impact Testing - Number of Tests and Locations -

See Main Steam Line Safety Relief Valves.

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v Page 7 of 13 d.- Bolting Materials - Charpy V-Notch Testing ~- See Main Steam.Line-Safety. Relief Valves,

e. Documentation and Maintenance of QA Program: See Main Steam -Line Safety Relief Valves,

f. Design Stress Intensity Values No change in design stress intensity values for . valve body material.

Design

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a. Standard and Alternate' Design Rules - See Main Steam Line Safety Relief- Valves.

b. Prevention of Nonductile Failure - See Main Steam Line Safety Relief Valves.

Fabrication and Installation

a. Impact' Tests - See Main Steam Line Safety Relief l Valves.

b. Qualification of Forming and Bending Process - See Main Steam .Line Safety Relief Valves.

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c. . Impact Tests of Weld Deposits - See Main Steam Line i Safety Relief Valves.

d. Time Temperature Recordings - See Main Steam Line '

{ Safety Relief Valves..

Testing a

f a. Hydrostatic Testing - See Main Steam Line Safety Relief-Valves.

H. Equipment: Main Steam Line Pipe

Purchase Order Date

January 27, 1972 i

Code of Construction: ASME III, 1971 Edition with

! Summer '1971 Addenda.

4 Code of Comparison: ASME III, 1971 Edition with Winter 19 72 Ad de nda. .

l Analysis of Dif ference:

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a. Fracture Toughness - (1) NB-2311 - Requires addi-tional pressure - retaining components be impact tested.

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O Page 8 of 13 (2) NB-2322.2 - Outlines impact test specimen orientation requir ements for each product form in addition to plate forms.

(3 ) . NB-2332 - Requires impact testing at or below the lowest service temperature ,

except that bolting shall be tested at 40 *F. or lower; in lieu of previous requirement for impact testing at 60 *F below the lowest service metal temperature or lower.

(4) NB-2332 (a) (1) - Sets forth acceptance of impact test data based on mils lateral expansion, in lieu of previously used absorbed energy.

(5) NB-2332 (a) (2) - Adds impact testing for the heat af fected zone and weld metal from weld procedure qualification tests, in addition to previous requirement to test base materials and weld metal.

(6) NB-2360 - Specified calibrat.on frequency requirements for instruments and test machines in lieu of previously specified intervals.

b. Chemical Analysis: NB-24 32 - Incorporates requ.i re-ment for chemical analysis on all weld filler metals and/or deposits, in addition to previous requirement for ferious alloy A-7 and A-8 materials.

Design

a. Nonductile Failure: NB-3611.5 - Introduces requirement for prevention of nonductile failure at eme rgency and f aulted loading conditions.

b. Qualification by Burst Tests: NB-3612.l(b) -

Intr) duces specific requirement for maintenance of burst test records.

c. Stress Indices: NB-3 6 8 3. 2 Introduced revised or added values for stress indices.

Fabrication and Installation

a. Forming and Bending Processes: NB-4212 -

Established requirements for qualification and requalification of procedures for bending and forming materials.

b. Specially Designed Welded Seals: NB-4360 -

Incorporates new welding procedure, not previously covered.

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Page 9 of 13 Examination

a. Specially Designed Welded Seals: NB-5271 -

i Incorporates examination requirements for welding L procedure not previously covered.

Testing

a. Specially Designed Welded Seals: NB-6127 -

Incorporates testing requirements for welding

! procedure not previously covered.

I. Equipment: Main Steam Line Flow Element Purchase Order Date: February 5, 1973 Code of Construction: ASME III, 1971 Edition with Summer 1972 Addendum.

Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda.

Analysis of Difference:

Materials

a. Chemical Analysis - See Main Steam Line Pipe.

Design

a. Qualification by Burst Tests - See Main Steam Line Pipe.

J. Equipment: Reactor Recirculation System Pump Purchase Order Date: May 7, 1971 Code of Construction: Nuclear Pump and Valve Code, l 1968 Edition with 1970 Addenda.

l Code of Comparison: ASME III, 1971 Edition with Winter l

1972 Addenda.

Analysis of Dif ference:

General Requirements

a. Stress Reports - See Reactor Pressure Vessel

b. Manufacturer's Responsibilities: See Main Steam Line Safety Relief Valves.

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Page 10 of 13

c. Quality Assurance: See Main Steam Line Safety Relief Valves.

d. N-Type Symbol Stamp: See Main Steam Line Safety Relief Valves.

Materials

a. Bolting Materials - Charpy V-Notch Testing - See Main Steam Line Safety Relief Valves.

b. Documentation and Maintenance of QA Program:- See Main Steam Line Safety Relief Valves,

c. Design Stress Intensity Values - No change in design stress intensity values for pump body material.

Design

a. Design of Class 1 Pumps: NB-3400 - Incorporates additional design criteria for Class 1 pumps, not previously covered.

b. Acceptability of Large Pumps: NB-3411(a) and 3211(d) - Introduces General Design Rules and Analysis requirements, and requirements for protec-tion against nonductile fracture, not previously covered.

Testing

a. Hydrostatic Testing - See-Main Steam Line Safety Relief Valves.

K. Equipment: Reactor Recirculation System Shut-Off

Valves Purchase Order Date

February 23, 1971 Code of Construction: Nuclear Pump and Valve Code, 1968 Edition with 1970 Addenda.

Code of Comparison: ASME III, 1971 Edition with Winter 1972 Addenda.

Analysis of Difference:

General Requirements

a. Stress Reports - See Reactor Pressure Vessel

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b. Manufacturer's Responsibilities: See Main Steam Line Safety Relief Valves.

c. Quality Assurance: See Main Steam Line Safety Relief Valves.

d. N-Type Symbol Stamp: See Main Steam Line Safety Relief Valves.

Materials

a. Bolting Materials - Charpy V-Notch Testing - See Main Steam Line Safety Relief Valves,

b. Documentation and Maintenance of QA Program: See Main Steam Line Safety Relief Valves.

c. Design Stress Intensity Values - No change in design stress intensity values for valve body material.

Design-

a. Standard and Alternate Design Rules: See Main Steam Line Safety Relief Valves.

b. Prevention of Nonductile Failure: See Main Steam Line Safety Relief Valves.

Testing

a. Hydrostatic Testing - See Main Steam Line Relief Valves.

L. Equipment: Reactor Recirculation System Pipe Purchase Order Date : February 25, 1971 Code of Construction: ASME III, 1968 Edition with Summer 1970 Addenda.

! Code of Comparison: ASME III, 1971 Edition with Winter l

1972 Adde nda .

l Analysis of Difference:

l General Requirements

a. Stress Reports ' - Incorporates additional require-ments to review and certify stress reports.

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b. Responsibilities for Quality Assurance: NA-3 360 ( a )

- Incorporates additional requirements to survey and qualify subcontractor QA programs.

Materials

a. Welding and Brazing Materials: NB-2400 - Specifies mechanical property tests and chemical analysis tests on each heat, lot and batch of welding materials.

b. Repair by Welding: NB-2539 - Restricts the repair of weld defects to cavities which :fter defect removal do not exceed 1/3 of the section thickness.

c. Required Examination: NB-2541 - Specifies use of radiography for forgings where ultrasonic methods are unacceptable,

d. Products Welded with Filler Material: NB-2560 -

Incorporates requirenent for NPT Code Symbol Stamps and inspection by an authorized inspector.

Design

a. Qualification by Burst Tests: See Main Steam Line Pipe.

b. Emergency Conditions: NB-3655 - Incorporates pres-sure and stress limits for emergency conditions, not previously covered.

l c. Faulted Conditions: NB-3656 - Incorporates pres-sure and stress limits for evaluating faulted l

conditions, not previously covered.

d. Stress Indices - See Main Eine Pipe, and revised limitation for f - inside and out-side reinforcement.

Fabrication and Installation

a. Specially Designed Welded Seals - See Main Steam Line Pipe.

l Examination

a. Specially Designed Welded Seals - See Main Steam Line Pipe.

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a. Specially Designed Welded Seals - See Main Steam f Line Pipe.  :

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