ML20137F543
| ML20137F543 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/07/1986 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137F549 | List: |
| References | |
| 2452N, SL-161, TAC-60542, NUDOCS 8601170548 | |
| Download: ML20137F543 (8) | |
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Georgia Power Company i
333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526 7020 Maihng Address:
Post Office Box 4545 Attanta, Georgia 30302 Georgia Power J. T. Beckham, Jr.
the southern electre system Vice President and General Manager Nuclear Operations g(_jg]
2452N January 7, 1986 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller,. Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington,'D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE-TECHNICAL SPECIFICATIONS-PROPOSED CHANGES-TO REACTOR VESSEL TEMPERATURE AND-PRESSURE-LIMITS Centlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1)', Georgia Power Company (GPC) hereby proposes change to the Technical Specifications, Appendix A to Operating License DPR-57.
These changes are being proposed to update the Technical Specifications pertaining to the reactor pressure vessel test specimens and the reactor pressure vessel temperature and pressure limits for pressure tests (such as required by ASME Section XI), non-nuclear heatup/cooldown, core critical operation, and vessel stud tensioning to reflect the test results from the first reactor surveillance capsule removed from the Hatch Unit 1 reactor pressure vessel in November 1984. provides a detailed description of the proposed changes and circumstances necessitating the change request. ' details the basis for our determination that the praposed changes do not constitute an unreviewed safety question. details the basis for our determination that the proposed changes _do not involve significant hazards considerations.
a provides page change instructions for incorporating the proposed changes into the Hatch Unit 1 Technical Specifications.
The proposed changed Hatch Unit 1
Technical Specifications pages follow.
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GeorgiaPower d Director of N1 clear Reactor Regulation Attention: Mr. D. Miller, Project Director
'BWR Project Directorate No. 2 Jamary 7,1986 Page Two Nineteen (19) copies of General Electric topical report NEDC-30997, "Edwin I.
Hatch M1 clear Ibwer Plant, Unit 1,
Reactor Presaire Vessel Surveillance Materials Testing and Fracture 'Ibughness Analysis," dated October 1985, which alpports this reglest, are being transmitted under separate cover.
Payment of the filing fee of $150.00 is enclosed.
R1ralant to the recuirements of 10CFR50.91, Mr. J.
L.
Iedbetter of the Environmental-Protection Division of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is althorized to execute this oath on behalf of Georgia Ibwer (bmpany, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA IUdER (DMPANY By:
~
J.p.Beckham,Jr.
Sworn to and subscribed before me this 7th day of Jaruary,1986.
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Notary Puut/, Crorgia, State at Large Notary Riblic
~ %Commisy.cn Expires Aug26,1986 JAE/ht Encloaire xc:
H. C. Nix, Jr.
Senior Resident Inspector J. N. Grace (NRC-Region II)
J. L. Iedbetter 700775
7 ATTACffiENT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 BASIS FOR-CHANGE REQUEST
' During the 1984 maintenance / refueling outage at Hatch Unit 1, the first reactor vessel surveillance capsule, containing flux wires for neutron fluence measurement and charpy and tensile test specimens for material property evaluation, was removed from the vessel for testing.
The changes proposed by this amendment update the Hatch Unit 1 Technical Specifications pertaining to the reactor vessel test specimens, the reactor vessel pressure teets (such as required by ASME Section XI),
~
non-nuclear heatup/cooldown, core critical operation, and vessel stud tensioning to reflect the results of tests conducted by the General Electric Company (GE).
Subsequent to the completion of testing, GE issued topical report NEDC-30997, "Edwin I.
Hatch Nuclear Power Plant Unit 1,
Reactor Pressure Vessel Surveillance Materials Testing and Fracture Toughness Analysis" to Georgia Power Company (GPC).
The subject topical report will be submitted by GPC to the NRC under separate cover.
The proposed changes to the Technical Specifications are based _ on the test results from the analyses (using approved methods and the requirements of 10 CFR 50, Appendix H, ASTM-E185, and Regulatory Guide 1.99, Revision 1) of specimens removed from the Hatch Unit 1 reactor vessel.
Significant differences exist in the present-day methodology used to establish the reference temperature of nil-ductility transition (RTNDT) as compared to methodologies in existence when the vessel was fabricated.
The GE analysis includes methods for converting the Hatch 1 fracture toughness data to comply with current NRC requirements.
The GE methodology, discussed in section 3.2.4 of NEDC-30997,'has been reviewed and approved by the NRC.
The new proposed limits derived from GE's analysis -will, if met, assure that the reactor vessel does not fail due to brittle fracture.
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ATTACINENT 2 NRC DOCKET 50-321 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 10-CFR-50.59 EVALUATION Pursuant to 10 CFR 50.59, the Plant Review Board has reviewed the.
attached proposed amendment to the Hatch Unit 1 Technical Specifications and has determined that implementation of the proposed amendment does not constitute an unreviewed safety question.
The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR because the changes propose new temperature and pressure operating limits on the Hatch Unit 1 reactor vessel based on the test results of specimens (i.e.,
flux wires, charpy V-Notch impact test specimens, and uniaxial tensile test specimens) removed from the vessel in
. Hovember 1984. - The proposed operating limits are based on the analyses of the specimens using the methods described in 10 CFR 50 Appendix H,
. ASTM-El85, and P,egulatory Guide 1.99, Revision 1, and meet the requirements of 10 CFR 50 Appendix G.
No plant equipment or system, other than the reactor vessel, is affected by the proposed changes.
The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result because no new modes of operation are introduced.
The proposed changes place new limits on pressure and temperature on the Hatch Unit 1 reactor vessel thus ensuring that it will not fail due to brittle fracture. The new limits were calculated using approved methods and meet the requirements of 10 CFR 50, Appendix G, thus, the possibility of vessel failure due to incorrect operating limits is not introduced.
The margin of safety as defined in Technical Specifications is not reduced since the proposed changes maintain the margin of safety by imposing new limits on reactor vessel temperature and pressure to account for the increase in reference temperature calculated from test results from specimens removed from the Hatch Unit I reactor vessel in November 1984.
These new limits meet the requirements of 10 CFR 50, Appendix G.
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. ATDOIMENr 3' NRC DOOTT 50-321 EDWIN I.' HAT 01 NUCLEAR PLANT UNIT 1
- 10 CER 50.92 EVALUATION R1ralant to 10 CER 50.92, Georgia Power Conpany has evaluated the attached proposed; amendment for Hatch Unit _1 and has determined that its
. adoption ~walld_ not involve.a significant hazard.
We basis for-this determination is as follows:
i PROPOSED OIANGES Revise the operating tenperature and pressure' limits in Hatch Unit 1-Technical Specification section.3.6.B, 3.6.C, 4.6.B, and their associated operating tengerature-presaire limit alrves to reflect the resilts of tests condacted on reactor; vessel alrveillance specimens removed from the Hatch
. Unit 1 reactor vessel per the realirements of 10 CER Appendices G and H.
~ BASIS'
%e proposed changes to the Technical Specifications add more stringent
- operating tenperature and presaire limits to the Technical Specifications
- than = those which previalsly existed.
As a reallt, the - proposed ' change is consistent with Item (ii). of the " Examples that are Considered Not Likely to
. Involve Significant Hazards Considerations" listed on page 14,870 of the
- April-6,1983 isale'of the Federal Register.
% e. proposed changes do not add a significant increase-in the probability or consea2ences of an accident previously evaluated because the
-new, more stringent operating tenperature and presaire limits are based on
' the reallts of tests' cond1cted on reactor vessel alrveillance spcimens removed from the Hatch Unit 1 reactor vessel.
Use of these new operating temperature and presaire limits will help to enaire that the reactor vessel does not fail die to brittle fracture.
W e proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated since no new modes
.of failure are introd1ced by imposing new operating tenperature and presaire limits on the Hatch Unit 1 reactor vessel.
PRO 10 SED OIANGES Revise ~ the " List of Figures:" and the " Bases" sections (Technical Specification bases sections 3.6.B and 3.6.C) of the Hatch Unit 1 Technical Specifications to reflect new operating temperature and presaire limits rea11 ting from tests conducted on reactor vessel alrveillance specimens removed from the Haten Unit l' reactor vessel per the recuirements of '10 CER 50 Appendices G and H.
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ATTAQiMENT 3 (contimed)
BASIS
%e. proposed changes to the " List of Figures" and Bases sections 3.6.B
-and 3.6.C in the Hatch Unit 1 Technical Specifications are administrative in p
nature.
As a result, the proposed changes -are consistent with Item (i) of the " Examples of Amendments that are (bnsidered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983 isale of the Federal Register.
%e proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated beca1se the changes are being made to reflect the changes in operating temperatures and presaire limits rea11 ting from tests conclicted on reactor vessel alrveillance specimens removed from the Hatch Unit 1 reactor vessel.
-%e proposed changes do not involve a significant recliction in the margin.of safety since they are administrative in nature and merely reflect the imposition of new operating temperature and pressure limits on the Hatch Unit 1 reactor vessel which actually enhance the margin of safety.
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ATIAGMENT 4 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I HA'1DI NUCLEAR PLANT UNIT 1 RECUEST 'IO REVISE 'IECHNICAL ' SPECIFICATIONS -
PROIOSED WANGES 'IO REACIOR VESSEL 'IDIPERA'IURE AND PRESSURE LIMI'IS
'1he proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:
Remove Page Insert Page n
x 3.6-1 3.6-1 3.6-2 3.6-2 Figure 3.6-1 Blank page, original figure deleted Figure 3.6-2 Ficpre 3.6-1 Figure 3.6-3 Ficpre 3.6-2 Figure 3.6-4 Figure 3.6-3 3.6-15 3.6-15 3.6-16 3.6-16
- 3. 6-17 3.6-17 y
l LIST OF FIGURES Figure
- Title
~1.1-1 Core 'Ihermal Power Safety Limit Vera2s Core Flow Rate 2.1-l' Reactor Vessel Water Ievels 4.1-1.
Graphical Aid for the Selection of an Adequate Interval Between Tests 4.2-1 System Unavailability 3.4-1 Sodium Pentaborate Solution Volume Vera2s Concentration Requirements 3.4-2 Sodium Pentaborate Solution Temperature Verals Concentration Reg 2irements 3.6-1 Presaire verals Mini: nim Tenperature for Presaire Tests, Such as Realired by ASME Section XI 3.6-2 Presa2re verals Mininum Tenperature for Non-N2clect Heatup/Cooldown and Iow Ibwer Physics Test 3.6-3 Press 2re verals Mininum Temperature for Core Critical Operation other than Iow Power Physics Tests (Includes 400F Margin Req 2 ired by 10CER50 Appendix G) 3.11-1 (Sheet 1) Limiting Value for APIHE (Riel Type 3) 3.11-1 (Sheet 2) Limiting Value for APIHGR (Riel Types 1 and 2) 3.11-2 deleted 3.11-3 Kg Factor 3.15-6' Unrestricted Area Boundary 6.2.1-1 Offsite Organization 6.2.2-1 Unit Organization j
HA'IUI - UNIT 1 x
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