ML20133B207
| ML20133B207 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/30/1985 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0896, RTR-NUREG-896 SBN-876, NUDOCS 8510030080 | |
| Download: ML20133B207 (7) | |
Text
1' SEABROOK STATION Engineering Office d
September 30, 1985 New Hampshire Yankee Division SBN-876 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC NUREG-0896, " Safety Evaluation Report, Related to the Operation of Seabrook Station, Units 1 and 2", dated March 1983
Subject:
SER Outstanding Issues; Materials Engineering Branch (MtEB)
Concerns
Dear Sir:
In t.he Seabrook Station's Safety Evaluation Report (SER), the staff indicated that there were several MtEB issues still left unresolved. In our efforts to close out all remaining licensing activities on this project, we are herein, via Attachment A, including the responses to those issues still unresolved in SER Sections 4.5.1, 4.5.2, 5.2.3, and 6.1.1.
Additionally, we have provided in Attachment B a status list of active MtEB review items. Presently, we are still active in closing out the open issues regarding the Preservice and Inservice Inspection Programs, and we believe that we have sufficiently addressed the remaining MtEB issues with information provided herein.
Our assessment of the eleven unresolved MtEB SER issues indicates there are nine issues which require evaluation and action by your staff. We are anticipating a submittal in the near term that should resolve our remaining PSI /ISI issues.
The Seabrook Project would very much appreciate any effort on your staff's part to include the resolution of these outstanding items in the next 8510030000 850%O ADOCK 0%g3 PDR p\\
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(
P.O. Box 300 Seabrook, NH O3874. Telephone (603)474-9521 1
United States Nuclear Regulatory Commission Attention:
Mr. George W. Knighton Page 2 supplement to the'Seabrook Station's SER. Should you or your staff require any additional support regarding these issues, please do not hesitate to contact us.
Very truly yours, J. DeVincentis, Director Engineering and Licensing Attachments ec: Atomic Safety and Licensing Board Service List s
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L LVilliam S. Jordan, III Donald E. Chick
' Dinne Curran Town Manager Harmon,. Weiss & Jordan
, Town of Exeter-20001 S. Street, N.W.
10 Front Street f
Suite 430.
Exeter, NH 03833 Washington, D.C.
20009 Brentwood Board of Selectmen
- Robert C. Perlis RED Dalton Road Office of the Executive Legal Director Brentwood, NH 03833 U.S. Nuclear Regulat'ory Commission Washington, DC. 20555 Richard E. Sullivan, Mayor City Hall 4-Robert A. Backus, ~ Esquire Nemburyport, MA 01950
'126 Lowell Street P.O. Box 516 Calvin A. Canney Manchester, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street E,
Assistant Attorney General Portsmouth, NH 03801
', Augusta, ME 04333 Dana Bfsbee, Esquire
,kgf - Mr. John B.- Tanzer Assistant Attorney General
" Designated Represe~ntative of Office of the Attorney General the Town of' Hampton 206 State House Annex 5 Morningside Drive Concord, NH 03301 Hampton, NH 03842 Anne Verge, Chairperson Roberta C. Pevear Board of Selectmen Designated Representative of
. Town Hall South Hampton, NH 03827 the Town of Hampton Falls s
Drinkwater Road
-Hampton Falls,'NH 03844 Patrick J. McKeon Selectmen's office
.l'
.Mrs. Sandra Gavutis 10 Central Road Designated Representative of Rye, NH 03870 the Town of Kensington RFD 1 Carole F. Kagan, Esquire East Kingston, NH 03827.
Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Jo Ann Shotwell, Esquire Washington, DC 20555 Assistant Attorney General Environmental Protection Bureau Mr. Angi Machiros Department of the Attorney General
. Chairman of the Board of Selectmen One Ashburton Place, 19th Floor Town of Newbury Boston, MA 02108 Newbury, MA 01950 Senator Gordon J. Humphrey Town Manager's Office y
U.S. Senate Town Hall Friend Street 4 -
Amesbury, MA 01913
'j'
,.(ATTN: Tom Burack)
Washington, DC 20510
.3' Senator Cordon J. Humphrey Diana P. Randall 1 Pillsbury Street 70 Collins Street Concord, NH 03301 Seabrook, NH. 03874 (ATTN: Herb Boynton) d a
I E
SBN-876 ATTACHMENT A Responses to Previously Unresolved'MtEB Issues A. -
SER'Section 4.5.1 Concern-(C-7)
The applicant must confira.that the aging and tempering temperatures of heat treatable materials in the CRDM are in accordance with staff guidelines.
c
Response
All heat treatable materials'in the CRDM are classified as Non-Nuclear 7, -
-Safety and, therefore, do not fall under the requirements of the ASME B&PV Code. These non-nuclear safety heat treatable materials are primarily 410 SST components which are heat treated in accordance with ASTM specifications or other Westinghouse internal material procurement specifications. The minimum heat treatment temperature of the stainless steel materials in the CRDM was equal to or greater.than 10500F.
B.
SER Section 4.5.2 Concern (C-7)~
The applicant must confira that the aging and tempering temperature of heat treatable materials of the reactor internals are in accordance with staff guidelines.
-Response The heat treatable materials used in the reactor internals are made of Inconel X750 (SA 637,-Grade 688). The aging and tempering of the Inconel X750 (SA 637, Grade 688) materials is performed in accordance with Westinghouse Specification A637C01. This heat treatment is modified slightly from the heat treatment specified in SA 637 in order to develop the material properties required for Westinghouse PWR service conditions. All subsequent testing and examinations are performed in accordance with ASME B&PV Code,Section III, Subsection NG.
-C..
SER Section 5.2.3 Concern N. 1 (0-9) o The applicant has not provided required fracture toughness data and has not demonstrated compliance with 10CFR50, Appendix G, for the RCPB Materials..The applicant must provide evidence of compliance' for staff review.
Response
FSAR Sections 5.2.3.3 and 5.3.1.5 sufficiently describe t'he fracture toughness of the ferritic RCPB materials and provide evidence of compliance with 10CFR50, Appendix G.
A minor change in our FSAR Amendment 55, Section 5.2, clarifies the location of the required fracture toughness. data.
A-1 g
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Responses to Previously Unresolved Mt'EB Issues (Continued) n L
D.
SER Section 5.2.3 Concern N. 2 (C-ll) o i
The applicant has not addressed limiting RCPB components constructed of
.austenitic stainless steel to a maximum strength of 90,000 psi.
This
'must be confirmed to provide the staff with a basis for evaluating the assurance of RCPB integrity.
i
Response
Austenitic stainless steels used in the construction of the RCPB components are used in the annealed condition and, therefore, do not have a yield strength greater than 90,000 psi.
E.
SER Section 6.1.1 Concern (C-10)
The applicant must address the adequacy of the fracture toughness of ESF components made of ferritic steels considering their function and environmental conditions associated with normal operation, maintenance, testing, and postulated accidents.
Response
All ferritic steels used for the Engineered Safety Features a,re tested and certified to the requirements of the ASME B&PV Code,Section III.
The required testing, as dictated by the rules of Section III, has been' 1
Eperformed for each heat of material used and documented on Certified I
Material Test Reports. These reports are part of'the final QA data package for each component.
.y A-2
SBN-876 ATTACHMENT B Status of Unresolved MtEB Issues Required SER Section Description SER Issue Action By Remarks 4.5.1 Confirm aging /
C-7 S
See Attachment A, tempering T of heat.
Response Item A.
treatable materials in CRDM are in accordance with staff guidelines.
4.5.2 Confirm aging /
C-7 S
See Attachment A, tempering T of heat Response Item B.
treatable materials in reactor internals are in accordance with staff guidelines.
-5.2.3 Staff to completu 0-9 S
See FSAR review of submittal Amendment 47, on compatibility of Page 6.1(B)-2 the thermal ~ insulation with RCPB materials in accordance with RG1.36.
5.2.3 Provide required 0-9 S
See Attachment A, fracture toughness Response, Item C.
data in compliance with Appendix G for RCPB materials.
5.2.3-Confira RCPB C-7 S
See Attachment-A, components (austenitic Response Item D.1 SS) maximum yield strength is 90,000 psi.
6.1.1
.ESF materials, C-10 S
See Attachment A, supply information to Response Item E.
address adequacy of fracture toughness of
- components of ferritic
-steels.
B-1
1 Status of Unresolved MtEB Issues (Continued)
Required SER Section Description SER Issue Action By Remarks 10.2.3 Turbine inspection -
C-1 S
Applicant has (3.5.1.3)
GE turbine disc committed to second integrity inspection refueling inspection program, subject to which utilizes.GE's NRC's approval.
inspection program.
Staff to indicate applicant's use of GE inspection program is acceptable, based on staff evaluation of the GE inspection program.
10.3.6 Main steam and C-32 S
Submitted in PSNH feedwater system Letter SBN-661, dated material fracture June 1, 1984.
toughness properties meet GDC 35.
10.3.6-Provide rationale 0-9 S
Submitted in PSNH justifying waiving Letter SBN-661, dated of fracture toughness June 1, 1984.
testing of ferritic steel components on MS and FW Systems.
5.2.4, Inservice Inspection LC-4 A
Inservice inspection 6.6.1 Program.
0-4 information will be provided at a future date.
5.2.4.1 Preservice Inspection 0-4 A
Preservice inspection Program.
information will be provided at a future date.
,e
. LEGEND:
C - Confirmatory 0 - Open LC - License Condition A - Applicant S - Staff B-2 l
L: