ML15112A934
| ML15112A934 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/01/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A935 | List: |
| References | |
| NUDOCS 8008280312 | |
| Download: ML15112A934 (15) | |
Text
o UNITED STATES NUCLEAR REGULATORY COMMISSION 00 z
WASHINGTON, D. C. 20555 August 1. 1980 Dockets Nos..50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.
Vice President - Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
The Commission has issued the enclosed Amendments Nos. 85,
85, and 82 for Licenses Nos. DPR-38, DPR-47 and DPR-55 for the Oconee.Nuclear Station, Units Nos. 1, 2 and 3. These amendments consist of changes to the Station's common Technical Specifications (TSs) and are in response to your submittal dated July 31, 1980. Your request of July 31 was stated to be needed due to a power shortage in your service area that may continue through mid-August 1980. We verified through the U. S. Department of Energy the power needs for your service area and the VACAR electrical grid, of which Duke Power Company is a part. We agree you are operating with marginal reserve gener ating capacity through mid-August 1980.
These amendments revise the Technical Specifications by temporarily extending the allowable period-of inoperability of the "2B" High Pressure Injection Pump for Unit 2 until August 15, 1980.
Copies of the Safety Evaluation and the Notice of Issuance are also enclosed.
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosures:
- 1. Amendment No. 85 to DPR-38
- 2. Amendment No. 85 to DPR-47
- 3.
Amendment No. 82 to DPR-55
- 4. Safety Evaluation
- 5. Notice of Issuance cc w/enclosures:
See next page 7590-01, For further details with respect to this action, see (1) the application for amendments dated July 31, 1980, (2) Amendments Nos.
85, 85, and 82 to Licenses Nos. DPR-38, DPR-47 and DPR-55, respectively, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N. W., Washington, D. C. and at the Oconee County Library, 201 South Spring Street, Walhalla, South Carolina. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 1st day of August 1980.
FOR THE NUCLEAR REGULATORY COMMISSION ert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing 9e
UNITED STATES NUCLEAR REGULATORY COMMISSION 7590-01 DOCKETS NOS. 50-269, 50-270 AND 50-287 DUKE POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendments Nos.
85, 85, and 82to Facility Operating Licenses Nos. DPR-38, DPR-47, and DPR-55, respectively, issued to Duke Power Company (the licensee), which revised the Station's common Technical Specifications for operation of the Oconee Nuclear Station, Units Nos. 1, 2 and 3, located in Oconee County, South Carolina. These amendments are effective as of the date of issuance.
These amendments revise the Technical Specifications for Unit No. 2 by extending n a temporary basis the allowable period of inoperability of the "2B" High Pressure Injection Pump through August 15, 1980. This action was due to a potential power shortage in the Duke Power Company service area.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR §51.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
0Il
Oconee 1/2/3
-2 Otherwise, only one.HPI pump, assuming single failure of the remaining pump, would be required. With Pump "A" operating and Pump "C" on standby, it is required that valve HP-26 which is normally closed, open on'receipt of an engineered safeguards (ES) signal.
To reduce the probability Iof this valve failing to open on signal, an operator would be stationed to ensure the valve does open on receipt of an ES signal.
We have verified with the U. S.'Department of Energy, the cognizant Federal agency concerned with adequacy of electrical power ayailability,.that the Duke Power Company service area and the VACAR subregion of the Southeastern power distribution region has practically no electrical energy reserves when con sumption is at the expected peaks in the time period to August 15, 1980.
As the request is onlyfor a duration of 15 days, and conditioned to power needs, the low probability of the most limiting small break (0.04 to 0.10 sq.
ft.), and the compensating factor of stationing an operator to verify the opening of valve HP-26, we conclude that this temporary TS change is acceptable.
Environmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4 that an environmental impact statement, or negative declaration and environ mental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that: (1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a signi ficant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: August 1, 1980
- toUNITED STATES f,
NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO.85 TO FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO.82 TO FACILITY OPERATING LICENSE NO. DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS NOS. 1, 2 AND 3 DOCKETS NOS. 50-269, 50-270 AND 50-287 Introduction By letter dated July 31, 1980, the Duke Power Company (licensee) requested a temporary Technical Specification (TS) change for the Oconee.Nuclear Station, Unit.No. 2 (Oconee-2). The proposed change would revise TS 3.3.1, High Pressure njection (HPI) System, Section c.(2)(b).
ackground HPI pump 2B failed on July 26, 1980; on July 29, 1980, a replacement pump also failed; the licensee reduced power to 60% as required by TS 3.3.1.
The failure of the first pump is due to the impeller shifting on the pump shaft and binding on the pump casing. The pump manufacturer, Ingersoll-Rand, has two service representatives at Oconee who are working to both determine cause of failure of the second pump and to attempt repairs of one of the failed pumps. Due to the severe hot weather in the Oconee service area and the marginal ability of the electrical utilities in thearea to meet their power demands, the licensee requested this temporary change to permit 100% power operation of Unit 2, on a conditional basis, through August 15, 1980. Pump repairs or replacement will not be complete before that date.
Evaluation Of the remaining two HPI pumps, the "A" pump is in operation for system make-up and reactor coolant pump seal injection flow. The "C" pump is in standby; this, pump was verified operable on July 17, 1980. The licensee stated all power supplies, instrumentation and controls, and auxiliary support systems for the HPI system are operable.
Three HPI pumps are required to be operable only in the event of (1) a limiting single failure in the HPI system, and (2) a postulated break in the primary cold leg Jepiping of between 0.04 and 0.10 sq. ft. in the vicinity of the HPI nozzle for which the HPI flow is assumed lost and failure of one of the HPI pumps.
3.3.1.c.(2)(c)T (Temporary Technical Specification)
For Oconee 2, HPI pump B, the requirements of Specification 3.3.1.c.(2)(b) are amended as follows:
Conditions where upon Oconee Unit 2 may be escalated to 100% FP in order to meet expected peak demand.
- 1. All Duke system generation capability has been utilized to the maximum extent available.
- 2. All available purchases from other VACAR utilities have been utilized.
- 3. All available purchases from outside the VACAR subregion have been utilized.
If all of the above conditions are satisfied and the total available generation capacity is not expected to be sufficient to meet the expected peak load and the required spinning reserves, then Oconee 2 will be escalated in power up to 100% FP.
This Temporary Technical Specification will expire at 11:59 p.m. on August 15, 1980.
Amendments Nos.
85, 85 & 82 3.3-2a (TEMPORARY)
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
85 TO DPR-38 AMENDMENT NO.
85 TO DPR-47 AMENDMENT NO.
82 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A by adding page 3.3-2a (Temporary). When this temporary specification has expired, this page should be removed.
1
0 0
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-55 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing Attachment, Changes to the Technical Specifications Date of Issuance: August 1, 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION 0,
WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 31, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health-and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is-in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment, and paragraph 3.8. of Facility Operating License No. DPR-47 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of I-ssuance: August 1, 1980
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A* The application for amendment by Duke Power Company (the licensee) dated July 31, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
I
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-38 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ro ert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 1, 1980
- g 0
o~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 31, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;.
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
(III
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Mr. Robert B. Borsum Duke Power Company Babcock & Wilcox P. 0. Box 2178 Nuclear Power Generation Division 422 South Church Street Suite 420, 7735 Old Georgetown Road Charlotte, North Carolina 28242 Bethesda, Maryland 20014 Oconee Public Library Manager, LIS 201 South Spring Street NUS Corporation Walhalla, South Carolina 29691 2536 Countryside Boulevard Clearwater, Florida 33515 Honorable James M. Phinney County Supervisor of Oconee County J. Michael McGarry, III, Esq.
Walhalla, South Carolina 29621 DeBevoise & Liberman 1200 17th Street, N.W.
Washington, D. C. 20036 Director, Technical Assessment Division cc w/enclosure(s) and incoming dtd.:
Office of Radiation Programs July 31, 1980 (AW-459)
U. S. Environmental Protection Agency Office of Intergovernmental Relations Crystal Mall #2 116 West Jones Street Arlington, Virginia 20460 Raleigh, North Carolina 27603 U. S. Environmental Protection Agency Region IV Office ATTN: EIS.COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U. S. Nuclear Regulatory Commnission P. 0. Box 7 Seneca, South Carolina 29678
REG&
JCENSE AUTHORITY FILE GOP UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.
D. C. 20556 August 1, 1980 Dockets Nos.(i9i D50-270 and 50-287 Mr. William 0.
Parker, Jr.
,4
/k-a Vice President - Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
The Commission has issued the enclosed Amendments Nos. 85,
85, and 82 for Licenses Nos. DPR-38, DPR-47 and DPR-55 for the Oconee Nuclear Station, Units Nos. 1, 2 and 3. These amendments consist of changes to the Station's common Technical Specifications (TSs) and are in response to your submittal' dated July 31, 1980. Your request of July 31 was stated to be needed due to a power shortage in your service area that may continue through mid-August 1980. We verified through the U. S. Department of Energy the power needs for your service area and the VACAR electrical grid, of which Duke Power Company is a part. We agree you are operating with marginal reserve gener ating capacity through mid-August 1980.
These amendments revise the Technical Specifications by temporarily extending the allowable period of inoperability of the "2B" High Pressure Injection Pump for Unit 2 until August 15, 1980.
Copies of the Safety Evaluation and the Notice of Issuance are also enclosed.
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosures:
- 1. Amendment No. 85 to DPR-38
- 2. Amendment No. 85 to DPR-47
- 3.
Amendment No. 82 to DPR-55
- 4. Safety Evaluation
- 5. Notice of Issuance cc w/enclosures: See next page