ML18018A553

Forwards QA Branch & Matls Engineering Branch Requests for Addl Info Not Addressed in Feb 1983 Draft Ser.Info Requested by 830701

ML18018A553
Person / Time
Site:	Harris
Issue date:	05/03/1983
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Utley E CAROLINA POWER & LIGHT CO.
References
NUDOCS 8305230296
Download: ML18018A553 (9)

Text

Sea MAY 3 1983 I R y DISTRIBUTION' f.-C 1~50-400/401 NRC PDR L PDR NSIC Docket Nos.:

'50-400 and 50-'401 Nr. E.

E. Utley Executive Vice President Carolina Power 5 L>,ght Company Post Office Box 1551 Raleigh, North Carolina 27602 LB¹3 Reading JLee NPKadambi At'torney, OELD

Jordan, IE Taylor, IE ACRS (16)

TNNovak

Subject:

Request for Additional Information - Shearon Harris Enclosed are,two sets of requests for additional information which were not covered in the Draft Safety Evaluation Report issued in February 1983.

Enclosure 1 is the set from the guality Assurance Branch (Reviewer:

Jack Spraul) and Enclosure 2 is the set from the Materials Engineering Branch (Reviewer:

David Smith). It would be appropriate to add the listed items to the Open Items List in Chapter f'of the DSER.

Please provide the information requested by July 1, 1983, or in the alternative, inform us as to those items for which such a schedule cannot be met.

Please contact the Project ttanager, Prasad Kadambi, at (301)492-8423 regarding any questions.

Sincerely,

Enclosures:

As stated Qytgtng @9086 b1I'oogga

'g. KnittMln George H. Knighton, Chief Licensing Branch No.

3 Divjsion of Licensing cc:

See next page 8305230296 830503 PDR ADOCK 05000400 E

PDR DL:LB¹3gPg

~ ~ ~ o ~ o ~

~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~

~

NPKadambi /v oooo ~ ~ oo ~ oo ~

~ ~ ~ ~ ~ ~ oTo ~

5/L/83 OFFICEI SURNAME Q DA7E P

~ oooooooooooo

~ ~ o ~ o ~ ~ ~ o ~

D

~ ~ ~ o p

o ~ ~ ~ ~ ~ ~ ~ o ~

G iqhton

~ ~ \\ o o ~ o~o ~ o Ko ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5/

/83 NRG FOAM 318 (10-80) NRCM 0240 OFFICtAL RECORD COPY USOPO: 198~-

L I

(

L gl

Shearon. Har'ri s Mr. E.

E. Utley Executive Vice President Power Supply and Engineering and Construction Carolina Power

& Light Company Post Office Box 1551

Raleigh, North Carolina 27602 CC:

George F. Trowbridge, Esq.

Shaw, Pittman, Potts Trowbridge 1800 M Street, NW Washington, DC 20036 Richard E. Jones, Esq.

Associate General Counsel Carolina Power

& Light Company 411 Fayetteville Street Mall

Raleigh, North Carolina 27602 M. David Gordon, Esq.

Attorney Associate General State of North Carolina P. 0.

Box 629 Raleigh, North Carolina 27602 Thomas S. Erwin, Esq.

115 W. Morgan Street Raleigh, North Carolina 27602

'Mr. George thxwell Resident Inspector/ Harris NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 315B New Hill, North Carolina 27562 Charles.D. Barham, Jr.,

Esq.

Vice President

& Senior Counsel Carolina Power

& Light Company Post Office Box 1551 Ral eigh;. North Carol ina 27602

r. John-Runkl'e," Executive'oordinator onservation Council of North Carolina 307 Granville Road Chapel Hill, North Carolina 27514

r. Hells Eddleman 8-A Iredell Street Durham, North Carolina 27705

~r..'G~orge Jackson Secretary Environmental Law project School of Law, 064-A University of North Carolina Chapel Hill, North Carolina 27514 Dr. Phyllis Lotchin 108 Bridle Run Chapel Hill, North Carolina 27514 Mr. Travis Payne, Esq.

723 W. Johnson Street P. 0.

Box 12643

Raleigh, North Carolina 27605 Mr. 5aniel F.

Read, President'HANGE P. 0.

Box 524'hapel Hill, North Carolina 27514 Ms. Patricia T.

Newman, Co-Coordinator ter. Slater E.

Newman, Co-Coordinator Citizens Against Nuclear Power 2309 Meymouth Ct.

Raleigh, North Carolina 27612 Richard D. Wilson, M.D.

725 Hunter Street Apex, North Carolina 27502 Regional Adminstrator - Region II U. S. Nuclear Regulatory Commission 101 t1arietta Street Suite 3100 Atlanta, Georgia 30303 Karen E. Long, Esq.

Staff Attorney Public Staff -

NCUC Post Office Box 991

Raleigh, North Carolina 27602

ATTACHMENT 1 Harris Request for Additional Information equality Assurance Branch Section

17. 1.2.2 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures,

systems, and components controlled by the gA program.

You are requested to supplement and clarify the Harris FSAR in accordance with the following:

The following items do not appear on FSAR Table 3.2.1-1.

Add the appropriate items to the table or justify not doing so.

1.

Containment emergency sumps 2.

Equipment hatch and personnel air locks 3.

Guard pipes and leak-tight compartments for containment emergency sump recirculation lines and valves 4.

Engineered safety features actuation system 5.

Charcoal filters in the control room HVAC system 6.

Fuel building radiation monitor 7.

Roof and site drainage system including drains, parapets, grading, culverts, and channels 8.

AC Onsite Power Systems (Class 1E)

Oiesel generator governor, voltage regulator, and excitation system Instrumentation, control, and power cable splices, connectors, and terminal blocks Conduit and cable trays and their supports which do not contain Class 1E cables but whose failure may damage other safety-related items Load sequencer AC control power inverters AC vital bus distribution equipment 9.

OC Power Systems (Class 1E)

Conduit and cable trays and their supports which do not contain Class 1E cables but whose failure may damage other safety-related items Battery racks Protective relays and control panels 10.

Radioactivity sampling (air, surfaces, liquids) ll.

Radioactivity contamination measurement and analysis equipment 12.

Personnel monitoring equipment (internal, e.g.,

whole body

counts, and external, e.g.,

TLD system) 13.

Instrument storage, calibration, and maintenance program 14.

Decontamination facilities, personnel, and equipment r

15.

Respiratory pr otection equipment (including testing) 16.

Contamination control b.

Clarify Table 3.2. 1-1 as noted below or justify not doing so.

Provide a commitment that all safety-related instrumentation and controls (I&C) described in FSAR Section

7. 1 through 7.6 and other safety-related I&C for safety-related fluid systems will be subject to the pertinent requirements of the FSAR Appendix 8 gA program.

This can be done by a footnote to FSAR Table 3.2.1-1.

2.

Under "Electrical Systems and Components" on FSAR Amendment 3 page 3.2. 1-43 is "Safety-related power control and instrument cables and raceways."

It appears that a

comma should be inserted after "power" and one after "control."

3.

Notes 26 and 27 to FSAR Table 3.2. 1-1 state that some re-quired information can be found in Table 11.4.2-1.

Table 11.4.2-1 does not have this information, and clarification is needed.

c ~

FSAR Amendment 3, on page 3.2. 1-42, includes "Post Accident Monitoring Instrumentation NUREG 0737."

However, Enclosure 2

of NUREG-0737 identified numerous other items that are also safety-related or of such importance to safety that. they should have the pertinent requirements of the FSAR Operational gA program applied.

These items are listed below.

Provide such a commitment in Table 3.2. 1-1 of the FSAR or justify not doing st

~ f'

1.

Plant-safety-parameter di spl ay console 2.

Reactor coolant system vents 3.

Plant shielding 4.

Post accident sampling capabilities 5.

Yalve position indication 6.

Auxiliary feedwater system 7.

Auxiliary feedwater system initiation and flow NUREG-0737 (Enclosure 2)

Clarification Item I. D.2 II.B. 1 II.B.2 II. B. 3 II.D.3 II.E.1.1 II.E.1.2 8.

Emergency power for pressurizer heaters II.E.3.1 9.

Dedicated hydrogen penetrations 10.

Containment isolation dependalility

11. Instrumentation for detection of inadequate core-cooling 12.

Power supplies for pressurizer relief valves, block valves, and level indicators II.E.4.1 II.E.4.2 II.F.2 II.G.1

13. Automatic PORV isolation 14.

PID controller

15. Anticipatory reactor trip on turbine trip 16.

Power on pump seals 17.

Emergency plans 18.

Emergency support facilities

19. Inplant I~ radiation monitoring

20. Control room habitability II. K. 3.1 II. K.3.9 II. K. 3. 12 II. K.3. 25 III.A.1. 1/III.A.2 III.A.1.2 III.D.3. 3 III.D. 3.4

ATTACHMENT 2 Request for Additional Information 252.0 Materials Engineering Branch - Materials Application Section 252; 1 Determine if there was a maximum yield strength specified for austenitic stainless

steels, and its magnitude (SRP 4.5..1 and 4.5.2).

252.2 For precipitation hardening and martensitic stainless

steels, state the aging and tempering treatments speci-fied (SRP'4.5.1 and 4.5.2).

252.3 Identify the materials used based upon Code Case 1618.

If the limitations of Regulatory Guide 1.85 are appli-cable, justify why the recommendations of the Regulatory Guide were not met (SRP 4.5.2).

252.4 Provide data and rationale as to the acceptability of the electroslag

'welds in steam generators 1 8, 2 (SRP 5.2.3, 5.4.2. 1, SRP 1..34, "Control of Electroslag Held 'Properties" ).

252.5 Ther'e have been many instances of underclad cracking in carbon-manganese steel pressure vessels made without fine grain melt practice or with high heat input weld processes.

Provide rationale and data to demonstrate that underclad cracking is not present, and if it is, that it is acceptable-(SRP 5.2.3 and 5..3.1, Regulatory'uide 1.43, "Control of Stainless Steel Weld C'ladding of Low-Alloy Steel Components" ).

252.6 Provide data and rationale as to the acceptability of the fracture toughness of ferritic steel components in

,the engineered safety features (SRP 6. 1. 1).

252. 7 Provide data and rationale why fracture toughness criteria were applied to Class 2 components of the main steam and feedwater systems and not applied to Class 3 components.

Also provide a rationale as to the acceptability of Class 3 components which were not produced to meet a fracture toughness criteria (SRP 10.3.6).

252.8 Identify materials by specification,

grade, type, etc.,

rather than by proprietary designations (SRP 4.5. 1 and 4.5.2).