ML19332F208
| ML19332F208 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/04/1989 |
| From: | Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Knighton G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AGM-NUC-89-261, NUDOCS 8912140039 | |
| Download: ML19332F208 (7) | |
Text
{{#Wiki_filter:n, 3x a w ,i Q, .e2 r )SMUD z }l1 Dd pN SACRAMENTO MUNICIPAL UTluTY DISTRICT C 6201 S Street, P.o. Box 15830 Sacramento CA 95852 1830 (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA '
- q AGM/NUC;89-261)
December /4,1989 U.'S.. Nuclear Regulatory Commission Attn:- Document Control Desk Washington, DC,20555 t Docket No. 50-312 ~ Rancho ~Seco= Nuclear Generating Station License No. DPR-54 1ECHNICAL SPECIFICATI0NS' APPLICABLE'IN ..M DEFUELED CONDITION - Attention: George Knighton 1 The-District.is defueling the Rancho Seco Nuclear Gcnerating Station and nis in en extended outage far an as yet undetermined duration. The movement of. spent fuel assemblies into the spent-fuel' pool- (SFP) is an activity previously analyzed and described in the-Updated Safety Analysis Y Report (USAR). L1he reinoval of all fuel from the Reactor Vessel and the Reactor Building results in the plant being in a condition that,.n1though bounded by the Modes-described.in Technical Specification Table 1.2-1, is i not specifically defined as a Mode in the Technical Specifications. i -Therefore, the District.has evaluated-the Technical Specifications to detdrmine which sections apply in' the defueled condition. Attachment 2 to.this~1etter presents the 'results of this evaluation, y iThe criteria used to determine the applicability of each Technical 'i -Specification section in the defueled condition was based, as a minimum, t Lon meeting thosc Specifications related' to the following: l'. Maintain spent fuel pool cooling. ~ e 2.= -Maintain offsite releases as low as reasonably achievable.
- 3.. Provide monitoring of offsite releases to ensure compliance with release limits.
g The~ District will maintain the Spent Fuel Pool Cooling (SFC) system OPERABLE in.accordance with Technical Specification 3.9. The SFC has .more than adequate capacity to reintain the pool temperature below the Technical. Specification -required 140*F. The SFC system design capacity a -of 8.76 million? BTU /HR greatly exceeds the de:ay heat load of 4 million .RT1MHR. The' system capacity is actually greater than this during the SW 2140039 89:2o4 -{DR ADOCK 05000312 [ 001 ~ PDC ~ g, - RANCHO SECO NUCLEAR GENERATING STATION D 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935 K ~;
t S P, 'e George Knighton AGM/NUC 89-261-winter months when the outside ambient temperature is below the design - madmum temperature, and as the outside ambient temperature increases in thi:oming summer months, the speat fuel pool heat load is calculated to l. decrease to 2.78 million BTU /HR by June 7, 1990. Hith'the reactor defueled and the fuel stored in the SFP the conservat h lineup for the Decay Heat Removal (DHR) system is to provide cooling fi - the SFP. The DHR system must be declared inoperable for purposes other j 1 than SFP cooling, pursuant to the requirements of Technical Specification 3.9.2, when the system is being used for cooling of the SFP. In addition, lechnical Specification 3.9.3 restricts the use of DHR for SFP cooling to no more than 100 hours per 12-month period when the plarit is not in Cold Shutdown. Technical Specification 3.9.3 is not considered applicable when the reactor is defueled since the DHR system is not required to be OPERABLE to satisfy other Technical Specifications. The 1 DHR s,r tei; will be maintained available in the defueled condition to-s serva as a backup SFC system. l t The Technical _ Specifications do not require t?e mergency power sources j be OPERABLE when the reactor is defueled. However, as a conservative j measure, the Bruce GM diesel generator and related buses associated with -l the available DHR train will be maintained available. The Bruce GM l diesel generator provides emergency power to the major loads associated j with DHR (DHR, Nuclear Service Cooling Hater (NSW), and. Nuclear Service l Raw Hater (NRW) pump motors). In addition, through the use of the q 480-voit cross-tie breakers (breakers 3A21 and 3A203, or 3B21 and 3B203 - as presented in Attachment 3), the Bruce GM Diesel' generator can supply i the remaining -loads required to maintain this conservative diesel generator backup ability. Thesa remaining loads are primarily environmental control loads such at the Nuclear Service Electrical Duilding (NSEB) and Control Room / Technical Su;, port Center (CR/TSC) Heating Ventilation and Air Conditioning (HVAC) systems. As illustrated in Attachment 3, the cross-tie breakers connect the two 480-volt buses within a train, and do not effect the independence of trains. Use of the 480-volt cross-tie breakers was previously analyzed and approved by.the } NRC as detailed in Technical Sp9eification Amendment Number 68. 4 Appropriate routine maintenance and testing will be performed on the: Bruce GM diesel generator being maintained to support the available DHR system. This will include testing equivalent to the following Technical i Specification tests: 1. 4.6.3.A.1,.2,.3, and.4 2. 4.6.3. A.5, (no fast starts will Se performed) 3. 4.6.3.B.1, .2, and.3 i a
G ] ] s GiorgeKnighton - AGM/NUC 89-261 j Start testing of.the Bruce GM Diesel generator will be performed quarterly in lieu of monthly. This frequency reduces unnecessary starts. while ensuring.the engine is available when needed. The likelihood of- -l needing diesel backup power.is very low since the probability of a total loss of offsite power at Rancho Seco, as stated in the District's April 17, 1989 submittal in response to 10 CFR 50.63 Loss Of Offsite Power, is less than once.in 20 years. The auto start and auto load capabilities of the Bruce GM diesel generator are not required to be kept in service'since there is a l significant amount of time available to start and load the diesel in the unlikely event of a loss of offsite power. District calculations, using the very conservative assumptions of Branch Technical Position APCSB 9-2, j show that it takes a minimum of 21.3 hours for the SFP to reach 140'F from an initial temperature of 110*F on a loss of SPC (see Attachment 1).. This time is valid.for December 5,1989. The 140*F limit is set to minimize' thermal stresses onsthe:SFP (see USAR section 5.4.2.1.5) but tne pool is capable of withstanding stresses up to and including those resulting from a pool temperature of 212'F. l Out-of-service time for systems being maintained available will be l controlled threugh " Administrative Action Statements" that will be y developed through an evaluation of.the effects of equipment and system unavailability. Until these evaluations are completed, a conservative 72 hour' limit will be set for each of the systems being maintained available. It is expected that the " Administrative Action Statements" will be periodically updated to reflect changes in the plant conditions. The Assistant General Manager, Nuclear shall have the responsibility for determining actions to be taken if one of these " Administrative Action Statements" will not be met. Those systems not being maintained OPERABLE or "available" as described l in this. letter, and not required for routine plant activities, will be L P' layed up in accordance with detailed plans developed by the. District. These plans incorporate vendor recommendations, industry experience, and sound engineering practices to provide for lonc-term protection and preservation of the systems for potential future use and are available on site.for review and inspection. These plans call for layup activities such as' hand rotation of rotating equipment to ensure bearings remain lubricated and free, draining and dehumidification of piping to reduce corrosion during storage, forced dry air ventilation of piping systems to-maintain a protective environment, continued purchase of ASTM qualified fuel oil for all four emergency diesel generators, etc. The Specifications listed on Altachment 2 to this letter will continue to be met which will ensure compliance with the requirements of the Rancho Seco Technical Specification in the defueled condition. It is anticipated that further refinement of the list provided in Attachment 2 will occur as conditions at the piant change. There refinements will be provided in writing to the NRC as they occur. The District will also
e--. - ~ - - -. O [/ ' 3', V u c . George Knighton-AGM/NUC 89-261 u rh submit-a set 6f. Defueled Technical Specification for NRC review e d approval in the'near future to further document the list of systems reqa. rad in the - defueled condition.. 1 '-Members of. your staf f with questions requiring additional information or clarification may contact Steve Crunk at (209) 333-2935, extension 4913. > Si ncerely,- k ])CZ7t===- l ha## Dan R.~Keuter Assistant General: Manager Nuclear 1 - Attach'ments. lcc'w/atch: J. B. Martin, NRC, Halnut Creek A..D'/.ngelo,,NRC, Rancho Seco i -l '? s x 1 r a
- ta
,i =. SPENT FU EL POOL Time to Reach 140-Degrees F-
- 70 J
Initial Pool Temperature: -1100F l k 60 - I 50 - + l E.- .g i a n e 40 - g L. Dars TIME (nours) - = I H ,l V 12/5/89 21.3 m.. ~ kl 1/3/90 24.3 i 2 30 - 6/7/90 31.3 i p 6/7/91 47.0 6/7/94 63.7 i e f 20 - i I 10 - 1 ^ i i O i i 6 j y -i ili '. l l. i. i i i i I Dec.5 June June June -June June j 1989 1990 Igg 992. 1993 1994 .. ~..
k[, ;. I ll F j c. ,r p 'I -ATTACHMENT 2 3 . Technical Specification Number lSehtion?1. Definitions 3.0
3.8.1 Monitor
R15028 oniy. Applicable When Moving, Fuel in the spent-l .3.8.12' j fuel storage area, ^
- 3.9;l
'3.9.5 3 12 Only for systems' required to be OPERABLE .3.14 ~ -3.15' 3.16' i '3.171 3.'181 3.21 ~3.22 3.23-23.24 3.25 3.26-3.29 R -4.0 ' Table 4.1-1 . Page 4.7b~#44a, 44b, 44d,145, 46, 47,'51, 63 (Table 4.1-2. '#8,9.10;11-Table 4.1-3
- 2, 4,u6, 8, 4.14 Only. for systems required to be OPERABLE 4.15'
) - 4.'18 L ' 4 '.19 4.201 i J. 4.21-4.22 4.25 4.26 ' 4. 2 7.- L4.28 s4.29 4.30 4.34 Section 5. Design Features Section 6.0 Administrative Controls (except 6.18) m f' h 4
ATTACHMENT 3-START-UPdi START-UPW2 wu ww . wm mm wm mm 6.9 K V 4.16 KV REACTOR CIRC. WATER COOLANT PP PP l ww NUCL. SERV. m m SUPPLY 4.16 KV ) ) ) a }NC.}N.O. }N.C. }N.O. }N.C. }N.O. }N.0. } KC. 4A2 4A 48 482 I I (4A204) N.C. N.O. N.C. N.O.
- N.O.
N.C. N.O. N.C. I (4B204) A A A A GEA2-GEA GE8 GE82 ((-X43A2 )"X43Al. " ",X4382 )", X4382 A l y } N.C. N.C. N.C. N.C. ! 3 A2 '_(3 A202) '3_A. 480V 381 480V 382.. (38202) ~ N.O. l' I N.O. N.O. I f- )(N.O.. I I ' (3821) (38203) 3A203) (3 A21) -I I. l a SIMPLIFIED SAFETY BUSSES DEPICTION AT POWER CONFIGURATION NOTEtSEE FIG.8.2-2 OF USAR FOR DETAILED l' DEPICTION. {. b .}}