ML20141K721

Forwards Request for Addl Info Re Submitting WCAP-14474, Analysis of 300 Degree Capsule from CP&L Brunswick Unit 2 Reactor Vessel Radiation Surveillance Program. Response Requested within 60 Days of Ltr Date

ML20141K721
Person / Time
Site:	Brunswick
Issue date:	05/23/1997
From:	Trimble D NRC (Affiliation Not Assigned)
To:	Hinnant C CAROLINA POWER & LIGHT CO.
References
TAC-M98710, NUDOCS 9705290341
Download: ML20141K721 (5)

Text

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May 23, 1997 Mr. C. S. Hinnant, Vice President Carolina Power & Light Company

Brunswick Steam Electric Plant l Post Offica Box 10429 Southport, North Carolina 28461

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - BRUNSWICK STEAM ELECTRIC PLANT (TAC NO. M98710)

Dear Mr. Hinnant:

By letter dated February 25, 1997, Carolina Power & Light Company (CP&L) submitted WCAP-14474, " Analysis of the 300 Deg. Capsule from Carolina Power &

Light Co. Brunswick Unit 2 Reactor Vessel Radiation Surveillance Program," for l NRC staff review.

As a result of examining this submittal as well as information from previous l CP&L submittals related to your reactor vessel material surveillance program,

! the staff has identified a need for additional information. The information l is described in the enclosed request for additional information (RAI).

i Please provide your response within 60 days of the receipt of this letter.

Sincerely, l (Original Signed By)

David C. Trimble, Project Manager j Project Directorate 11-1 l Division of Reactor Projects - I/II i Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324

Enclosure:

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j DATE 05/M/97 05/d/97 05/ 97 [/

COPY [f%No s/No es No 0FFICIAL RECORD COPY U 1 I 7d5290341 970523 PDR ADOCK 05000324 p PDR

Mr. W. R. Campbell Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

, Mr. William D. Johnson Ms. Karen E. Long l Vice President and Senior Counsel Assistant Attorney General Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry.W. Jones, Chairman Mr. Robert P. Gruber Brunswick. County Board of Commissioners Executive Director Post Office Box 249 Public Staff NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident Inspector U.S. Nuclear Regulatory Commission Mr. W. Levis l 8470 River Road Director Southport, North Carolina 28461 Site Operations Brunswick Steam Electric Plant Regional Administrator, Region II Post Office Box 10429 i U.S. Nuclear _ Regulatory Commission Southport, North Carolina 28461

Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. William H. Crowe, Mayor City of Southport Mr. Mel Fry, Acting Director 201 East Moore Street Division of Radiation Protection Southport, North Carolina 28461 N.C. Department of Environment, Health and Natural Resources Mr. Dan E. Summers 3825 Barrett Dr. Emergency Management Coordinator Raleigh, North Carolina 27609-7721 New Hanover County Department of l Emergency Management

! Mr. R.-P. Lopriore Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402 Carolina Power & Light Company Brunswick Steam Electric Plant Mr. T. D. Walt Post Office Box 10429 Director l

Southport, North Carolina 28461 Operations & Environmental Support Department Public Service Commission Carolina Power & Light Company State of South Carolina 412 S. Wilmington Street Post Office Drawer 11649 .

Raleigh, North Carolina 27601 Columbia, South Carolina 29211 Mr. K. R. Jury Mr. Milton Shymlock Manager - Regulatory Affairs U. S. Nuclear Regulatory Commission Carolina Power & Light Company Atlanta Federal-Center Post Office Box 10429 61 Forsyth Street, SW, Suite 23T85 Southport, NC 28461-0429 Atlanta, Georgia 30303 l'

, ENCLOSURE REQUEST FOR ADDITIONAL INFOAMATION REGARDING THE CAROLINA POWER AND LIGHT COMPANY'S BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 AND UNIT 2 REACTOR VESSEL NATERIAL SURVEILLANCE PROGRAMS

)

The staff noted during its review of Reference 1 that some information on the unirradiated material properties of the material in the Brunswick Steam Electric Plant Unit 2 (BSEP-2) surveillance program were not reported. Specifically, on page 24, Table 5-7 indicated that the 30 ft-lb Charpy test transition temperature, the 50 ft-1b Charpy test transition temperature, the 35 mil lateral expansion Charpy test transition temperature, and the Charpy Upper Shelf Energy were "not available for the unirradiated surveillance program materials." These values were not available for the surveillance plate material (from Lower Intermediate Shell Plate 301), the surveillance weld material, or the surveillance heat affected zone (HAZ) material.

Subsequently, the staff examined Reference 2 and noted that the same information was  !

not reported for the surveillance materials in the Brunswick Steam Electric Plant 1 Unit 1 (BSEP-1) surveillance program. However, Appendix F to References 3 and 4 and l i section 5.3.1.6 of the Brunswick Updated Final Safety Analysis Report (UFSAR) indicate that some amount of surveillance material has been maintained by licensee l

at plant site as archive material.  !

Appendix H to Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50 Appendix H), " Reactor Vessel Material Surveillance Program Requirements," states in its introduction that, "The purpose of the material surveillance program required by 1 this appendix is to monitor changes (emphasis added] in the fracture toughness I properties of ferritic material in the reactor vessel beltline region...which result from exposure of these materials to neutron irradiation and the thermal

environment." In Section III.1 of 10 CFR 50 Appendix H, it is noted that in order l to_ achieve this objective, " the surveillance program...must meet the requirements of the edition of ASTM E 185 (American Society for Testing and Materials Standard E l

185, author's note] that is current on the issue date of the ASME Code to which the reactor vessel is purchased." Finally, to do so (as further indicated on page 5.3.1-4 of the Brunswick UFSAR) the facilities would be required to comply with the 1966 edition of ASTM E 185 (E 185-66), which states in paragraph 3.3 that to

" establish the unirradiated mechanical properties, at least 15 impact and 3 tension l specimens shall be tested...."

l Based on the above information, the staff requests a response to the following i questions:

[1] Determine and state whether or not sufficient unirradiated Charpy impact l data exist to establish a full Charpy impact curve for the units' surveillance materials in the unirradiated state. In this process, the weld wire heat and flux should be determined for the BSEP-2 surveillance l weld, since this data has not been reported. The staff expects that the availability of additional unirradiated impact test data for the BSEP-1 and B3EP-2 surveillance materials (e.g. from other licensees, vendors, or fabricator records) will also be examined and any relevant data reported to

, the staff.

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• [2] Identify what surveillance program materials are available in archived storage at the plant. Indicate whether sufficient quantities of these i

materials are available in the form of fabricated Charpy specimens or as l unfabricated material to establish a Charpy curve per the requirements of l E 185-66. If, per question 1, sufficient data does not exist already, determine what activities will be taken to obtain sufficient data (if possible) by using this archived material and provide a schedule for l performing the necessary testing. i

[3] If a full Charpy impact curve cannot be established from t'he existing data l And if insufficient quantities of the archived surveillance materials exist i from which additional Charay tests can be run to obtain the necessary data, propose an alternative met 1odology which will accurately make use of the existing data (and any supplementary data) to bring the BSEP 1 & 2 reactor vessel surveillance programs into compliance with ASTM 185-66 and 10 CFR 50 Appendix H. Provide additional data from materials similar to those found in the BSEP 1 & 2 surveillance program to demonstrate that this methodology provides an accurate assessment of expected material properties changes due to the irradiation and thermal effects.

It should be noted, hcwever, that per 10 CFR 50.60(b), approval of an alternative to 10 CFR 50 Appendix H will require an exemption. This exemption request should be submitted in accordance with the requirements of 10 CFR 50.12 along with the technical justification to support this alternative methodology.

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.. 1 REFERENCES

1. Letter from W.H. Campbell (CP&L) to the United States Nuclear Regulatory Commission Document Control Desk, " Brunswick Steam Electric Plant, Unit No. 2, Docket No. 50-324/ License No. DPR-62, Reactor Vessel Naterial Surveillance Specimen Test Results" with attachment, WCAP-14474, " Analysis of the 300 Dog Capsule from Carolina Power & Light Co. Brunswick Unit 2 Reactor Vessel Radiation Surveillance Program," February 25, 1997.

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2. Letter from R.P. Lopriore (CP&L) to the United States Nuclear Regulatory ,

Commission Document Control Desk, " Brunswick Steam Electric Plant, Units Nos. I and 2, Docket Nos. 50-324 & 50-325/ License Nos. DPR-71 & DPR-62, Submittal of Reactor Vessel Material Surveillance Specimen Test Results for Brunswick Unit 1" I with attachment, SR-BNPI-1005-001, " Brunswick Unit 1 PRV Surveillance Program  !

First Capsule (300*) Removal After 8 Fuel Cycles, Test Results and Projections,"  !

August 17, 1994.

3. NEDO-24157, Revision 2, "Information on Reactor Vessel Naterial Surveillance Program, Brunswick Steam Electric Plant Unit 2," June 1994.

' 4. NEDO-24161, Revision 1, "Information on Reactor Vessel Naterial Surveillance l Program, Brunswick Steam Electric Plant U11t 1," June 1994. l

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