ML19259C534
| ML19259C534 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane |
| Issue date: | 05/07/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUDOCS 7906260195 | |
| Download: ML19259C534 (120) | |
Text
{{#Wiki_filter:. 50-320 Miscellaneous documents from f1RR files dealing with Oconee as it relates t0 TMI 4/26/79 - 5/7/79 tIHIS DOCUMENT CONTAINS FOOR QUALITY PAGES 0 62601757
r y k /0COWEE TECH S /'E C S nom sEpwf T ER. ~ le STrxt & POWER CONVERSION SYSTT.M 3.4 ( Applicability Applies to the turbine cycle co=penents for removal of reactor decay heat. Ob'ective_ To specify cinimum conditions of the turbine cycle equipment necessary to assure from the reactor core. the capability to remove decay heat .i
- Specification The reactor shall not be heated above 250 F unless the following conditions 6
are met: de:ay heat lead of 5 percent full reactor power 3.4.1 Cap.bility to re= ave a from at least one of the following meanS: fcedwater p.cp. A hotwell pump, ccndensate bcoster pu=p, and a. air. a. b. The emergency feedwater pump. A hetwell pump and a condensate bcester pump. c. 3.4.2 The sixteen stea: system s4fety valves are operable. shall be avail-3.4.3 A =inimu of 72.200 g311sns cf witer per crerating unit able in the u;rer sur;e tani,
- ndensate s torage c irk, ind 5 *well.
The emergency cendenser cir cu;ating water system shall be operable as 3.4.4 per 2pecificatica 4.1. Sages The f eedwater system and the turbine bypass system are ncr: ally used f or decay retaval and cooldasn abcve 250 F. Feedwater takeup is supplied.by heat operatien of a hotwell pump, ccadensate 5 2oster pu:p and a =ain feedwater pump. The feedwiter f;;w required to recave decay heat corresponding to 5 percent full power with saturated steam in the pressure range frem 30 ;sta (saturation pressure at 250 f) to IC65 psia (le.est setting of atea= safety valve) as a 0 is: function of feedwater temperature F Flow, GPM 60 750 90 770 120 790 180 840 least 3J00 One hotwell pump plus one condensate booster pu=p will sup; 7-y -at plus one main 550 psia, and one hotwell pu=p plus cne booste. c._, GPM at 3.0"1 I
w t feed pu=p will supply at least 3000 gpm at 1065 psia. The e:ergency feed pu=p will supply 1050 gym at 1065 psia. In the event of cumplete loss of electrical power, feedwater is supplyed by a turbine driven energency feedwater pump which takes sucticn from the upper surge tanks and hotwell. Decay heat can be removed from the stea= generators by steam relief through the =ain stea: valves. Normally, decay heat is removed by stea= relief through the turbine bypass system to the condenser. Condenser cooling water flow is provided by a siphon effect f rom Lak e Keovee through the condenser for final heat rejection to the Kecwee Hydro Plant tailroce. The minimus arount of water in the upper surge tank and condensate storage tank is the amount needed for 11 hours of operating per unit. This is based on the conservative estimate of narcal makeup being 0.5; of throttle flow. Throttle flow at full load, 11,200,000 lbs/hr., was used to calculate the operation time. For decay heat re= oval the operation time with the volume of w2**r apecified would be considerably increased due to the reduced throttle flow. The relief capacity of the sixteen stea= system safety valves is 13,105,000 lbs/hr. REFERENCE FSAR, Section 10 s i i i I e s I i e s 3.a-2
k i DfERGENCY FEEDWATER PUMP PERIODIC TEST!NG 4.9 i 8 Applicability I u Applies to the periodic testing of the turbine-driven emergency feedvater pump. Obiective To verify that the emergency feedwater pump and associated valves are operable. w 4 Specification s 4.9.1 Test j s Quarterly, the turbine-driven emergency feedwater pump shall be operated on recirculation to the upper surge tank for a nini=um of one hour. 4.9.2 Acceptance Criteria These tests shall be considered satisf actory if c0ntrol boar d indication and that all cecpar.ents have visual observation of the emaipment de.onstrates eperated properly. { Bases The quarterly testing f requency is suf ficient to verify that the turbine-driven emergency feedwater pump is operable. Verification of carrect areratica visual airer-is made both from the centrol room instrumentation and direct ( vation of the pump. REFERENCES (1) FSAR, Sec ticn 10.2.2 (2) FSAR. Section 14.1.2.8.3 h 1 4.9-1 i i 4 e. l i I i
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May 9, 1979 hO v uu"ho h f U "' ' ' ' 2 '!'1 FO R : Harold R. Centon, Dircciar Of fice of Nuclar Reac tc c epla tion J.
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DRAFT D,'p( R w;;., J l1 i JN Ms. Sarnice Holt The Pal;.etto Alliance 13 Bluff Rc. I ~ Colc.bia, St.i.h Carolina 29501 Cea r s. 1:oi t : ' ted A;cil 27, 1979, :n T'.e C-
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' hal f of t'.e Pal:.etto Alliance to th Director of ::ucir ar Peccter 7.c.g u l.' M e n.~ : c . :sidera :. an on ;.. n t to lJ C R 2.F ^5 of the Cc. -icc :n's ru g :l a :.. .s. ? cur telcse m rcT.. ed t t '.'.e Cc cicq cc..r an d' s.%i& :q cf the M e F:.2r Cer, ny's Ccu a "ucicir Staa ;1, I!a i ts 1, 2,.. J 3, id ins ti : ution. ~ a t en - j., g '. o s 'r :..
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Enclosure:
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