ML19345A455
| ML19345A455 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/23/1966 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011210643 | |
| Download: ML19345A455 (3) | |
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UNITED STATES Formal
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R&PRSB Reading Orig: PENorian
%n ei DEC 2 319gg C. Henderson m nen.v ncren to; E. G. Case Docket No. 50-29 L. Kornblith (2)
N. D. Mason W. F. Nischan Yankee Atomic Electric Company 441 Stuart Street Boston, Massachusetts 02116 Attention:
Mr. Roger J. Coe Vice President Gentlemen:
This refers to your letter dated November 15, 1966 requesting a review by this office of a revision to the Technical Specific,ations attached as Appendix A to License No. DPR-3 for the Yankee reactor. This revision was requested to clarify the intent of the Technical Specifications in certain areas, and to up date certain portions as necessitated by operating experience and by previously approved changes to the Technical Specifications.
The specific changes to the Technical Specifications included in the revisien are as follows:
Section D.2.b Power Level (1) With all four main coolant loops providing normal flow to the core, the reactor power level is limited to 600 MW thermal.
(2) With only three main coolant loops providing normal flow to the the reactor power level is limited to 450 MW thermal.
- core, (3) The reactor will be scransned automatically by a high neutron flux level signal, set at not more than 1087. of rated powe. ;or each condition as defined in (1) and (2) above.
(4)
Except for operation ot' the reactor at plant power levels not ex-ceeding 15 MW electric, the reactor shall not be operated with less than three main coolant loops providing normal flow to the core.
(5) Whenever there is a sustained outage of one of the 115 KV lines because of maintenance g fault condition, the normally open cir-cuit breakers between the 2400 volt bus sections shall be arranged so that electrical power is available to supply all safety injection The reactor power level shall be reduced to a level consis-pumps.
tent with three loop operation as defined in (2) above.
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. DEC 2 31966 Section D.2.d Main Coolant System
.(3)
The reactor shall be scrammed automatically by a high pressurizer water level signal set at a maximum of 200 inches whenever the reactor power level exceeds 392 MW thermal.
(Change No. 6)
(6)
The plant shall not be operated at loads above 15 MW electric unless the boron concentration in the main coolant system ia less than 1700 ppm.
(Change No. 74)
(9)
Delete - The pressurizer spray line shall not be isolated when the reactor power level is greater than 5 MW thermal.
(Change No. 58)
(10)
Whenever a main coolant loop is isolated from the system, it shall be borated at full shutdown concentrations before it's temperature is reduced 30 F below the highest cold leg temperature of the operating loops.
Section D.2.f Plant Protection when the Reactor Vessel llend is Removed and the Vessel Contains Fuel (2)
Before flooding the shield tank cavity with borated water, it shall be determined that the boron concentration of the water in the Safety Injection Tank is not less than the required boron concen-tration of the main coolant system as defined in paragraph (4) below.
(7)
Equipment which would make possible inadvertant reactivity increases shall be made inoperable and tagged out of service.
(9)
During refueling two charging pumps and their associated valves and piping shall be available at all times to provide for addition of concentrated boric acid to the reactor pressure vessel.
Section D.2.g Waste Effluents (2)
Liquids - No radioactive liquid. wastes having concentrations in ex-cess of those specified in 10 CFR 20, shall be discharged from the plant.
(3)
Gases - As determined at the point of dischargo from the primary vent stack and averaged over a period not exceeding one year, the concentrations of radioactive gaseous wastes discharged shall not be in excess of 1000 times the limits specified in Appendix B, Table II, 10 CFR 20.
Any discharge to the atmosphere from the evaporator or the combustible' waste incinerator shall be con-tinuously monitored at or prior to the points of such discharge.
The monitor in the incinerator stack shall be kept in continuous service in order to provide an alarm and a record in the event of the release of radioactive gas from the vaste disposal blanket gas system through the loop seal.
(Change No. 52)
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.. DEC 2 31966 TABLE I REACTOR PROTECTION SET POINTS Function No. of Channels Remarks Required to Trip High Neutron 2 out of 5 or 6 Minimum of 4 operable Flux Level -
1 of 4 (single) channels required for Reactor Scram reactor operation High Pressurizer 1 out of 1 In service whenever Water Level -
reactor power level Reactor Scram exceeds 392 MW thermal.
(Change No. 6)
The above changes are either a clarification of the existing Technical Speci-fications or the incorporation of items previosuly approved pursuant to Section 50.59 of the Conunission's rules (10 CFR 50) except the change in Section D.2.
g(2) discussed below. The appropriate change number has been noted by those items authorized by previous changes to the Technical Specifications.
The only item in the above list which represents a revision in plant operation is the specification for liquid waste effluents (Section D.2.g(2)). The present provisions of Section D.2.g(2) limit the instantaneous release of liquid efflu-ents for various isotopes to the values specified in Appendix 2, Table II.
The proposed change in Section D.2.g(2) would permit averaging the discharge concentration of liquid effluents in accordance with Part 20 of the Canunission's rules (10 CFR 20). We believe that the clarifying changes set forth above and the proposed change to Section D.2.g(2) do not present signi-ficant hazards considerations not described or implicit in the hazards summary report, and that there is reasonable assurance that the health and safety of the public will not be endangered.
Accordingly, the revised Technical Specifications submitted with your letter of i
November 15, 1966 incorporating the above changes are approved.
I Sincerely yours, Peter A. Morris, Director Division of Reactor Licensing DRL
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