NL-89-598, Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station
| ML20246B288 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/31/1989 |
| From: | Crunk S, Mueller M SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NL-89-598, NUDOCS 8908230312 | |
| Download: ML20246B288 (7) | |
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' IO 'TSACRARN!NTD MUNICIPAL UTluTY DISTrilCT D 6201 S Street, P.O. Box 15830, Sacramento CA 95B524830,1916) 452-3211 j . AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA (
'NL-89-598.
% 1 Aug 101389 7
l U. S. . Nuclear.. Regulatory Commission
- Attn:s Document Control Desk ;
-Washington, DC 20555'
' Docket -No. 50- 312
. Rancho Seco Nuclear Generating Station License No.. DPR-54 OPERATING PLANT STATUS REPORT s-
-Attention: George:Knighton.
Enclosed is the July 1989 Monthly Operating Plant Statur Report for the Rancho Seco Nuclear Generating Station.' The District' submits'this report pursuant to Technical. Specification 6.9.3. Sincerely,: en Steve L. Crunk- . Manager. Nuclear Licensing
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.cc: J. B. Martin, NRC, Halnut Creek A. D'Angelo, NRC, Rancho Seco INPO R. Twilley, Jr.
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R [2 Mf I RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333 2935
JULY 1989 SUPMARY OF PLANT OPERATIONS Rancho Seco remains in cold shutdown following the negative outcome of the public vote on continued operation of the plant by SMUD. SUPMARY OF CHANGES IN ACCORDANCE HITH 10 CFR 50.59 The plant staff accepted documentation packages in July 1989 for the procedure changes and test described below which required detailed safety analysis. These changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).
- 1. Rancho Seco Administrative Procedure RSAP-0101, Revision 5, Nuclear Organization Responsibilities and Authorities, revised organizational titles and rearranged-area responsibilities. All safety review processes remain intact. This change does not make any physical modification to the plant nor does it change any operating procedures. The organizational changes comply with the " administrative control" requirements of Section 6 of the Technical Specifications. This procedure change does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nnr is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created. This procedure change does not involve an Unreviewed Safety Question.
- 2. Chemistry Procedure Manual CHM-1007. Revision 0, Biocide Evaluation for Circulating Cooling Water System, is the procedure for determining the effectiveness of liquid chlorine vs. liquid chlorine plus activated bromine-in controlling microbiological organisms and corrosion rates in the Circulating Hater System. Addition of Actibrom to determine its effectiveness in reducing the amount of chlorine required for circulating water disinfection is a test not described in the USAR. Because the circulating basin in not safety-related equipment, this test does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created. This test does not involve an Unreviewed Safety Question.
- 3. Process Standard AP.159, Revision 8, Bruce-GM Diesel Generator And Diesel Fuel Oil Systems, has been deleted. Limits and precautions from AP.159 have been incorporated into Operating Procedure A.31, Diesel Generator System. Because the limits and precautions are incorporated into A.31, the deletion of AP.159 does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created. This change does not involve an Unreviewed Safety Question.
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', SUlemRY OF CHANGES IN ACCORDANCE MITH 10 CFR 50.59 (Continued)
L 4. ' A' calculational mechanism was added to Radwaste Control Manual L . RP.309.IV.01, Revision.1, Transfer and Storage of Haste Containers in the IOS_ Building,Lto ensure.that the design basis report source term for the Interim Onsite Storage (105) Building is.not exceeded. Design Calculation
'#1-DC-262-601, concludes that with the present 6 inches of concrete in the Dry Activo Haste (DAW) Harehouse filled to capacity with all containers at the source term level,-the highest resulting dose due to sky' shine will be
- 9.4 mrem /yr. The. assumptions utilized in' the design of the IOS DAH l
Warehouse shielding and the methodology. employed in RP.309.IV-1 provide sufficient means to meet the regulations of 40 CFR 190. RP.309.IV.01, Revision 1, is not associated with safety. equipment. This; procedure does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously
-in the USAR created. This procedure change does not involve an Unreviewed Safety Question.
MAJOR SAFETY-RELATED MAINTENANCE. TESTS AND MODIFICATIONS NOT REQUIRING. DETAILED SAFETY ANALYSES
- 1. Modifications and maintenance of the Fuel Handling System continued in July 1989. Maintenance was performed on.the Nuclear P.aw Water System, Nuclear Service Hater System, "A" Decay Heat System,.TDI diesel generator, borated water storage system, large boiler, and main circulating water
-system. Installation and testing of fuel handling equipment to support defueling of the reactor.was begun.
- 2. ECN A-4764 Revision 2, made changes to the plant security system to-implement Amendment 11 changes 'to the Physical Security Plan. Under sub ECNs the following changes were made: changes to Auxiliary Building and NSEB doors including vital doors, emergency exits, and fire door instrumentation; added a card reader to Training and Records Building door TR604; relocated three CCTV cameras to view areas blocked by new construction; added a card reader to the Technical Support Center door.
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*- REFdELINGINFORMATIONREQUEST
- 1. Name_of._ Facility Rancho Seco 1
- 2. Scheduled date for~next refueling shutdown:
- E 3. : Scheduled date for restart following refueling: *
- 4. Technical Specification change or'other license amendment required:
- 5. ' Scheduled date(s) for submitting proposed licensing action:
- 6. Important licensing considerations associated with refueling:
- 7. Number of fuel assemblies:
a) In the core: 177 b)- In the Spent Fuel Pool: 316
- 8. -Present licensed spent fuel capacity: 1080
- 9. Projected date of the last refueling that can be discharged to the Spent' Fuel Pool: December 3. 2001
- Plant shut down June 7 following negative outcome of public vote regarding continued operation of Rancho Seco by SMUD.
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O"i M. AVERAGE DAILY UNIT. POWER LEVEL 2: . - . g.. ,1 DOCKET NO.- _ 50-312-
; s 4 - - UNIT Rancho Seco M
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DATE. 7/31/89 Lm s i -COMPLETED BY. Marla Mueller !%.u
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9 S TELEPHONE (916) 452-3211 , y-L o -u .: , , MONTH- July 1989' i! DAY. AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY' POWER LEVEL r
-(MHe-Net) 4
~ (MWe-Net) 1 0 17 0 t "' 2 0 ;18 0-D f' -3' -0 ' 19 - 0 LL 4- 0 20 0 5 ,
0 '21 0 L' 6~ 0 22 0 7 ~0 23 0
=8' O 24 0 9 0 25 0 10- 0 _ 26 0 a
11 0 27 0
~ 12 0 28 0
-- 0 29 0 14 0 30 0
- 15' -0 31 0 l16 ' 0 J
INSTRUCTIONS' On'this. format, list the average daily unit power level in MHe-Net for each day in'the reporting month. Compute to the nearest whole megawatt. NOTE:. Corrected number for June '7,1989 is 182 MHE-Net.
. _ . _ _ . _ . . . . _ . _ - . _ _ _ _ , _ - - - - . _ _ - - . . - _.-____.__n___-_____----_--
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" ' :0PERATING DATA REPORT;
$ DOCKET NO. 50-312~ 4 ,' DATE -7/31/89-a ' COMPLETED BY Marla 'Mueller
. TELEPHONE: '(916) 452-32i1 OPERATING STATUS-
- 1. . UnitL Name:~ . Rancho Seco . Notes:
- 2. . Reporting Period: . July 1989
- 3. - - Li ceased' Thermal ? Power (MHt): - '2.772 l
- 4. Nameplate Rating (Gross MHe): 963
- 5. ~ Design' Electrically Rating (Net MWe): 918
- 6. . Maximum Dependable Capacity.(Gross MHe): 917
- 7. Maximum Dependable Capacity-(Net MWe): 873
~8. -If> changes Occur in Capacity Ratings'(Items Number. 3 Through 7) Since Last Report.
N/A
~
Give Reasons:
- 9. Power-Level-to Which Restricted If Any (Net MWe): N/A
- 10.' - Reasons For Restrictions,- If Any: N/A This Month- .Yr-to-Date Cumulative:
111~. Hours;in Reporting Period 744 5.087 125.255-
- 12. ' Number of Hours' Reactor Has Critical 0 2.355.7 62.221.5-
- 13. Reactor Reserve Shutdown Hours 744 1.344.4 '11.644.6 14.- Hours Generator On-Line- 0 2.217.6 57.811.1
- 15. Unit Reserve Shutdown Hours 744 1.345.3 2.555.5
.16. Gross-Thermal Energy Generated-(MHH) 0 4.623.125 141.951'.953
- 17. : Gross- Electrical: Energy Generated (MHH) 0 1.575.699 46.223.924
-18. .. Net Electrical Energy Generated (MHH) -5.016 1.434.719 -42.478.602 119. ' Unit Service Factor 0% _ 43.6% -46.2%-
'20. Unit Availability Factor 100.0% 20.0% 48.2%
'21. Unit Capa';ity Factor (Using MDC Net) 0% _ -32.3% 38.8%
- 22. Unit Capacity Factor (Using DER Net) 0% L 2%_ 36.9%
- 23. Unit Forced Outage Rate 0% 40.7%
- 42.7%
- 24. Shutdowns Scheduled Over Next 6 Months (T,ype, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Pariod, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITTAL ELECTRICITY N/A N/A C 1,.ckCIAL OPERATION N/A N/A
- Plant shut down June 7 following negative outcome of public vote regarding ,
continued operation of Rancho Seco by SMUD. j i
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