ML19326A127
| ML19326A127 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/23/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19326A128 | List: |
| References | |
| NUDOCS 8002030007 | |
| Download: ML19326A127 (9) | |
Text
{{#Wiki_filter:. [: APPLICATION FOR AMENDMENT TO LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forth-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Technical Specifications, Appendix A to License No. NPF-3, together with the Safety Evaluation for the requested change.
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By .-M/40' -
' i d r' Vice President, Facilities Development Sworn to and subscribed before me this twenty-third day of October, 1978.
52 2 === Notary Public FRED W. GERMAIN Notary Public - State of Chio My Commission Empires Oct. 30,1982 _ f,s al b/7 8 0 02 0 3 0M] gg-
DB-1 REQUESTED CHANGE TO THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 TECHNICAL SPECIFICATIONS (appendix A to License No. NPF-3) The following attached pages have been :nodified to show the requested changes: Page 2-3 Page 2-5 Page 2-7 Page 2-8 Page B2-5 Page 3/4 2-14 Page 3/4 4-1 J al d/S Attachments Mu~ m i i r
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' CN/IS-GESSE. IJNIT T. . .
- 2. Anieric=ent No.'. .
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LIMITING SAFETY SYSTEM SETTINGS BASES
.iC High Temoerature The RC High Temperature trip < 619'F prevents the reactor outlet temperature from exceeding the desTgn limits and acts as a backup trip for all power excursion transients.
Flux - a Flux-Flow The pcwer level trip setpoint produced by the reactor coolant system ficw is based on a flux-to-flow ratio which has been established to accommodate ficw decreasing transients from high pcwer where pro-tection is not provided by the High Flux / Number of Reactor Coolant Pumps On Trips. The power level trip setpoint produced by the pcwer-to-ficw ratio provides both high power level and low ficw protection in the event the reactor power level increases or the reactor coolant ficw rate decreases. The power level setpoint produced by the power-to-flow ratio provides overpcwer DNB protection for all modes of pump operaticn. For every flow rate there is a maximum permissible power level, and for every pcwer level there is a minimum permissible low ficw rate. Typical power level and icw flow rate combinations for the pump situations of Table 2.2-1 are as follows:
- 1. Trip would occur when four reactor coolant pumps are operating 1 j f power is 105.5% and reactor ficw rate is 100%, or flow '
rate 'is 94.6% and pcwer level is 100%. ;
- 2. Trip would occur when three reactor coolant pumps are operating i if power is 78.3% and reactor flow rate is 74.7%, or ficw rate is 70.9% and power is 75%.
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- 3. Trip would occur when one reactor ccolant pump is operating in each loop (total of.two pumps operating) if the power is 50.6%
and reactor ficw rate is 49.0% or ficw rate is 46.3: and the power level is 49.0%. For safety calculations the maximum calibration and instrumentatien errors for the pcwer level were used.
%M DAVIS-BESSE, UNIT 1 B 2-5 m m 4
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o . . . 1 1 l li TAllt [ 3.2-1 e. I f. u IlNil HARGIN as g LlHITS
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. . four Reactor Three Reactor One Neactor j g Coolant Pimaps Coolant Pimps Coolant Piagi q Parameter operating operating operating _ in tach Ioop ..
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(2) Limit not applicalile sluring ef tlier a IlifillMt. P(RifR 4ings leicrease lei excess of 51 of
' HAllin lillHHAL POWtH per minute or a IllLPJiAL PuutR step increase of greater tinasi 10%
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3/4.4 REACTCR COOLANT SYSTEM REACTOR CCCLANT LOOPS LIMITING CCNOITION FOR OPERATION 3.4.1 Both reactor coolant loops and both reactor c:clant pumps in each lecp shall be in operatien. APPLICABILITY: As noted below, but excluding MCCE 6.* ACTION: HOCES 1 and 2:
- a. 'With one reactor c:olant pumo not in coeratien, STARTUP and
- PCWER OPERATION may :e initiated and may proceec proviced THERMAL POWER is restricted :: less than 78.3t of RATED q THERMAL POWER and within 4 hours the setacints for the following trips have been reduced tc the values s;ecified in Specification 2.2.1 for operation with three reac::r coolant pu=os operating:
- 1. High Flux
- 2. Flux-aFlux-Flow
- b. With one reacter c clant pumo in each loop not in c:eratien, STARTUP and-POWER CPERATION may be initi; ed and may roceed provided THERMAL POWER is restricted to less than 30.6tof h(
RATED THERMAL POWER and within 4 hcurs the set:cints fer the follcwing trips have been reduced to the values specified in Specification.2.2.1 for c:eration with one reac:ce coolant pump cperating in each loop:
- 1. High Flux -
- 2. Flux-aFlux-Flcw
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