ML20137Q392
| ML20137Q392 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/17/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Q372 | List: |
| References | |
| NUDOCS 8509200143 | |
| Download: ML20137Q392 (5) | |
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/ o g UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION
- 3 S E WASHINGTON, D. C. 20555
\.....] .
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPFPATING LICENSE Amendment No. 84 License No. DPR-25
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
A. The application for amendment by the Comonwealth Edison Company (the licensee) dated May 30, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
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B. The facility will operate in conformity viith the apolication, the provisions of the Act and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the ac'.ivities authorized by this amendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i
l D. The issuance of this amendment will not be inimical to the l
common defense and security or to the health and safety of the public; and i E. The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Comission' regulations and all applicable requirements have been satis #ied.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arendment and paragraphs 3.B. and 3.F of Facility Operatino License Fo. DPR-25 are hereby anended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 84 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificetions.
F. Deleted.
- 3. This license anendment is effective October 27, 1985.
FOP THE NUCLEAR REGULATORY CIMMISSION John . Zwolinski, Chief Operating Reactors Branch f5 Division of Licensing i
Attachment:
Changes to License.No. DPR-25 and the Technical Specifications Date of Issuance: September 17, 1985 l
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'4 ATTACPMENT TO LICENSE AMENDMENT N0. 84_
FACILITY OPERATING LICENSE DPR-25 -
DOCKET NO. 50-249
- 1. Revise License DPR-25 by removing page 4 and inserting the enclosed page 4.
I 2. Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 4
3/4.6-11 3/4.6-11 I
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DPR-25 4
- 3. E. Restrictions Operation in the coastdown mode is permitted to 40%
power. Should off-normal feedwater heating be' necessary for extended periods during coastdown (i.e.
Am. 42 greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) the Licensee shall perform a 4/16/80 safety evaluation to determine if the MCPR Operating Limit and calculated peak pressure for the worst case abnormal operating transient remain bounding for the new condition.
F. Deleted l G. The licensee may proceed with and is required to complete the modification identified in Paragraphs 3.1.1 through 3.1.23 of the NRC's Fire Protection Safety Evaluation (SE) dated March 1978 on the faci-Am. 33 lity. All modifications are to be completed by start-3/22/78 up following the 1979 Unit 3 refueling outage. In addition, the licensee shall submit the additional information identified in Table 3.1 of the SE in accordance with the schedule contained therein. In the event these dates for submittal cannot be met, the licensee shall submit a report, explaining the circum-stances, together with a revised schedule.
H. Physical Protection The licensee shall fully implement and maini..iu in
,_ effect all provisions of the following Commission approved documents, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
These approved documents consist of information withheld from public disclosure pursuant to 10 CFR 2.790(d).
- (1) " Security Plan for the Dresden Nuclear Power Station", dated November 19, 1977, as revised May 19, 1978, May 27, 1978, July 28, 1978 and l
February 19, 1979.
Am. 49 l 2/11/81 (2) "Dresden Nuclear Power Station Safeguards Contin-l gency Plan", dated March 1980, as revised June l 27, 1980, submitted pursuant to 10 CFR 73.40.
l The Contingency Plan shall be fully implemented, in accordance with 10 CFR 73.40(b), within 30 days of this approval by the Commission.
l 5039N 5039N 8403D Amendment No. 84 ,
DRESDEN III DPR-25 Amendment No, ff, 84 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT (Cont'd.) (Cont'd.)
- b. The indicated total core flow is more than 10% greater than the core flow value derived from established power-core flow relationships.
- 2. Flow indication from 2. Additionally, when each of the twenty operating with one jet pumps shall be recirculation pump, the verified prior to diffuser to lower plenum initiation of reactor differential pressure startup from a cold shall be checked daily shutdown condition. and the differential
, pressure of any jet pumps in the idle loop shall not vary by more than 10% from established patterns.
- 3. The indicated core 3. The baseline date flow is the sum of required to evaluate the flow indication the conditions in from.each of the Specifications 4.6,0.1 twenty jet pumps. and 4.6.G.2 will be If flow indication acquired each operating failure occurs for cycle.
two or more jet pumps, immediate corrective action shall be taken.
If flow indication for all but one jet pump a
cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
H. Recirculation Pump Flow H. Recirculation Pump Flow Mismatch Mismatch 3/4.6-11 3897a 3123A
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