ML20203L303

Monthly Operating Rept for Mar 1986

ML20203L303
Person / Time
Site:	Rancho Seco
Issue date:	03/31/1986
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-86-179, NUDOCS 8605010211
Download: ML20203L303 (8)

Text

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• AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 03-31-86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH March 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 -

27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO. 50-312 DATE 03/31/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS NOTE: The net electrical energy generated figures have been

1. Unit Name: Rancho Seco Unit 1 corrected to account for net

2. Reporting Period: ___ March 1986 negative station use during

3. Licensed Thermal Power (MWt): 2.772 outages.

4. Nameplate Rating (Gross MWe): 963

5. Design Electrical Rating (Net MWe): 918

6. Maximum Dependable Capacity (Gross NWe): 917

7. Maximum Dependable Capacity (Net MWe): 873

8. If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A

9. Power Level to Which Restricted, If Any (Net NWe): 0

10. Reasons For Restrictions, If Any: NRC limit pursuant to letter dated 12/26/85.

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 2.160 96.025

12. Number of Hours Reactor Was Critical 0 0 54.322

13. Reactor Reserve Shutdown Hours 0 0 10.300.2

14. Hours Generator On-Line 0 0 50.363.8

15. Unit Reserve Shutdown Hours 0 0 1.210.2

16. Gross Thermal Energy Generated (MWH) 0 0 127.861.688

17. Gross Electrical Energy Generated (MWH) 0 0 41.523.187

18. Net Electrical Energy Generated (MWH) -3.027 -12.187 38.317.915

19. Unit Service Factor 0.0% 0.0% 52.4%

20. Unit Availability Factor 0.0% 0.0% 53.7%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 45.7%

22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 43.5%

23. Unit Forced Outage Rate 100.0% 100.0% 32.1%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup: indefinite

26. Units In Test Status (Prior to Commercial Operation): Forecast /chieved INITIAL CRITICALITY N/A __N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

DOCKET NO. 50-312 .

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Rancho Secn Unit 1 DATE 3/31/86 COMPLETED BY R. Co1ombo REPORT MONTH March 1986 TELEPHONE (916) 452-3211 n.

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, 3? 'y jYj Licensee Eg ",, Cause & Corrective

.c g a: Action to gVi h Date R 3g  ;; Event g'!

5 mU Prevent Recurrence H

$= j if3 g Report a g 3

1 85-12-26 e 744 A 3 85-25 CB INSTRU Reactor trip on high pressure pre-ceded by a total loss of ICS power Corrective actions being implemented.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Screm. Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source 19/77) Il-Other (Explain)

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a 6 .e asuun me.e SACRAMENTO MUNICIPAL UTILITY DIST tlCT '_ 6201 S Street, P.O. Box 15830. Sacramento CA 95852:1'830.(9161452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA 333/R l3 n "e. y RWC 86-179 '

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April 14, 1986 J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE OF INSPECTION & ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE SUITE 210 WALNUT CREE; CA 94596 OPERATING PLANT STATUS REPORT DOCKET NO. 50-312 Enclosed is the March 1986 Monthly Operating Plant Status Report for Rancho Seco Unit No. One.

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R. W. COLOMB0 REGULATORY COMPLIANCE SUPERINTENDENT Enc 1 5 cc: I&E Washington (12)

MIPC (2)

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RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333 2935 hl

MARCH 1986

SUMMARY

OF PLANT OPERATIONS The plant has been in cold shutdown for the entire month of March. Initial shutdown was due to the December 26, 1985 loss of ICS event.

PERSONNEL CHANGES REQUIRING REPORT There were no changes.in personnel which require reporting pursusnt to Tech-nical Specification Figure 6.2-2.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 59.59 The final documentation packages for the following facility and procedure changes were completed in March 1986. All of the changes have been subjected to the review and approval of the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC). No final documentation packages for tests or experiments were completed during March 1986.

1. The Cycle 7 Reload Report, Volume 2, which is B&W Report BAW-1850, dated October 1984, has completed the formal documentation review process which included NRC approval as License Amendment No. 69, dated June 4, 1985. The entire B&W Report was previously provided to the NRC to suppert the proposed amendment which obviates the need to provide a summary of the Cycle'7 Reload Report in the Monthly Operating Report.

2. In order to provide greater operating flexibility, a third letdov!n cooler for the purification and letdown system has been installed. The new cooler is 100% capacity and has been designed as a Class 1 item. The new piping project class is the same as existing piping. A piping leak or rupture, or tube to shell leak will not create consequences any more severe than those resulting from the same accident in the existing system. Several existing motor operated valves were relocated to facilitate cooler isola-tion. The relocation of these motor operated valves will not change the original accident analysis for these valves. A pressure switch was added to detect tube to shell leakage in the cooler in a manner which is similar to the existing pressure switches for coolers E220 A and B. On high pressure, the switch will isglate primary coolant supply to the cooler.

Failure of the suitch will nci: effect safety features actuation of the valve. The piping modificati*ns resulted in adding two new hydraulic snubbers and the removal of o*e hydraulic snubber. This snubber addition precipitated a need to change;the technical specification list of snubbers which was completed by the ap$ oval of License Amendment No. 77, dated DecemberJ4,1985.

'I 3. In order to provide the ability to install a hydrogen recombiner after an accident as required by 10 CFR 50.44(c)(3)(ii), a modification was made to the plant to provide piping, isolation valves, shielding and new penetration l

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assemblies for lo' cations 60 and 67. A Nonconformance Report (N0. S3125)

' had been written addressing several technical: detail issues on the con- '

'- tainment penetration. assemblies. The nonconformance report was disposi -

tioned and a 10 CF.R 50.59 Safety Evaluation was performed. The new pene-- l l tration assemblies are fabricated of SA-516 plate, as opposed to forged assemblies as described as being typical in the USAR, and each of the alleged nonconformances were resolved. ,

, 4. In order to clarify the Emergency Action Levels.and the role of.the SMUD liaison at the Sacramento County-Emergency Operations Center,.and to re-l move all reference to the Herald Fire Station as a backup Emergency Opera-tions Facility (E0F), Revision 13 to Administrative Procedure (AP) 500 was approved. j l

i Emergency Action Levels (EALs) are used by the station operating staff to i

! classify station events into the emergency classification' system.- The l EALs were discussed in detail during Emergency Plan training sessions and l j comments-received from the Nuclear Operations Division and various Nuclear- i i Operations engineers. The changes to the EALs in Rev. 13 provide a i j clearer definition of the event and its relationship in the emergency. 1

! classification system. The EALs were not addressed in the FSAR or the l

Technical Specifications, and any change to plant procedures in this re- '

spect does not appear to be associated with plant nuclear safety related equipment in any significant way. The clarificatiun to the EAls is to

increase the speed and reliability of classifying the event into the ,

! emergency classification system and is designed to increase the level of public health and safety. ,

During a Notification of Unusual Event, th'e site Technical Support Centeri *

(TSC) would normally not be activated and the Sac. Co. E0C would be placed  ;

on standby. During an Alert, the TSC becomes operational. The E0F'is to

) be on standby, and the Sac. Co. E0C becomes operational. During the site

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4 area and General Emergency all facilities are operational. The emergency i j plan has the consnitment to send a SMUD representative to the. Sac. Co. E0C -

to assist in interpreting and responding'to the event. When the indivi-

,i dual would respond and who this individual is was not defined. The change i in Rev 7 identifies this individual as a member of the-E0F emergency .!

response sersonnel. The~ specific individual ~is'left up to the discretion >

I of the E0F Coordinator and is dependent upon the nature of the event. This >

individual.is.to respond to the' Sac. Co. E0C during an' Alert and will. remain

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< there until relieved, the close out of the Alert, or until the E0F becomes l

operational. When the EOF'becomes operational the'SMUD Liaison and a Sac.

i .Co. E0C Liaison will travel to the E0F. A SMUD Liaison is not~ required  :

at the Amador or San-Joaquin County E0Cs because of'their limited response

during the' Alert. -Amador and San Joaquin Counties become more actively. y involved during a Site Area Emergency, but.at.that-time the EOF will~be- j

. -come operational. The SMUD liaison was not: addressed in the FSAR or/the l

{ Technical Specifications, and.any change to plant procedures.in this respect e i does not. appear to be associated with plant nuclear safety related. equip- l

, ment in any significant way. The clarification'of-the SMUD. Liaison. . 1

[ position is designed to increase the level of-public health and safety.

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The California Division of Forestry Fire Academy in Ione and the Herald Fire Department Station are designated as the offsite assembly points.

When the initial drafts or NUREG-0696 were out for comment, the document specified a primary and backup E0F location. The Herald and Ione locations were upgraded to reflect this interim guidance. The final report of NUREG-0696, published February 1981, relaxed the E0F siting criteria such that a backup E0F was not required if the primary E0F was located at or beyond 10 miles of the'TSC. The Ione facility is 10 radial miles from the TSC. A backup E0F at Herald is not required or justified. The use of the Herald Fire Department Station as a backup E0F is not addressed in the

FSAR or the Technical Specifications, and any change to the plant procedures in this respect does not appear to be associated with plant nuclear safety related equipment or the public health and safety in any significant way.

l 5. In order to implement the proper d.esignation of responsibilities and staff-ing requirements requested by the NRC in letters dated 3/14/84 and 4/20/84, Item B.1, AP 500, Revision 16 was developed. Section 5.0 of the Emergency Plan (AP 500) now includes the requested specificity.

MAJOR ITEMS OF SAFETY RELATED MAINTENANCE

1. The Steam Generator Inspection Program has continued. The results of the inspection program, including the number of tubes plugged, the number and extent of tubes inspected, the location of an imperfection will be provided in the Monthly Operating Report following the completion of the program.

2. Repair efforts on the makeup pump P-236 continued. Currently plans include replacing the gear box and rotating element and repairing the pump casing.

3. The process of performing preventive maintenance on various plant valves, which were of particular interest to the Operations staff, has begun.

Approximately 40% of the selected valves have been maintained.

4. The reactor building post-accident sampling system and reactor coolant 4

post-accident sampling system are being refurbished to ensure reliable operatior..

5. The reactor building purge inlet valve was repaired by the replacing of the valve seat.

6. The emergency backup water supply (non-safety related) isolation valve

, (PCW-076) was maintained and leak tested.

7. The "B" diesel generator spare bypass lube oil pump was rebuilt, including new bearings gaskets, bushings, idler and shaft.

REFUELING INFORNATION REQUEST

1. Name of Facility Rancho Seco Unit 1

2. Scheduled date for next refueling shutdown: April 1. 1987

3. Scheduled date for restart following refueling: August 1. 1987

4. Technical Specification change or other license amendment required:

a) Change to Red Index vs Power Level Curve (TS 3.5.2) b) Change to Core Inhalance vs Power Level Curve (TS 3.5.2) c) Tilt Limits (TS 3.5.2)

5. Scheduled date(s) for submitting proposed licensing action: Oct. 1. 1986

6. Important licensing considerations associated with refueltag: N/A

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 i

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