ML20214N904

Monthly Operating Rept for Oct 1986

ML20214N904
Person / Time
Site:	Rancho Seco
Issue date:	10/31/1986
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-86-674, NUDOCS 8612040009
Download: ML20214N904 (9)

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OCTOBER 1986

SUMMARY

OF PLANT OPERATIONS The plant has been in cold shutdown for the entire month of October 1986. The initial shutdown was due to the December 26, 1985 loss of ICS power event.

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

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR PART 50.59 The final documentation package for the following facility and procedure changes were completed in October 1986. These changes were subjected to the review and approval of the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC) . There were no documentation packages completed for tests, or experiments during October 1986.

1. A five story Training and Records (T&R) Building was built to provide expanded and additional facilities for training, records, laboratory, and organization consolidation as required by NUREG's 0578, 0660, and 0667.

The presence of the building does not introduce a different type of accident, however its effect on adjacent Category I structures was considered. The structure was designed to meet the requirements of the Uniform Building Code and is designed so that the safe shutdown earthquake would not cause a structural failure.

This ensures that the T&R Building (Category II structure) would not collapse during the Safe Shutdown Event (SSE) and ensures that the T&R Building will not impair the adjacent Category I structures (i.e., Nuclear Services Electrical Building and the Auxiliary Building) due to a seismic event. Therefore, the consequences of a seismic event are unaffected by this structure being built. Thus, the margin of safety provided in the bases of Technical Specifications is unaffected.. (Log Number 396, Revision 0) .

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2. Redundant circuitry credited for safe shutdown with a l loss of off-site power was routed in conduits which run i

l between the NSEB and Auxiliary Building approximately 35 feet above grade level outside and separated by 60 feet.

The area the conduit runs across was not previously analyzed for Appendix R requirements.

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Evaluation of the Nonconforming Report associated with this deficiency concluded that the most prudent action was to provide a three hour fire rated barrier (wrap) for Train "A" circuitry. The Fire Protection Group established a new fire area (70) and declared it to be a Train "B" area (Train "B" is assumed lost in an Appendix R fire) and thus the Train "B" conduits will not be protected. A fire hazards analysis of the new fire area vill be incorporated into the next Fire Hazards Analysis Report update. (Log Number 781, Revision O)

3. A temporary PVC piping system was installed from the DRCST to the RHUT's with two isolation valves, a pump, and a flanged branch which allows for flushing of the temporary piping system with service water after each use.

The Deminerall' zed Condensate Storage Tank (DRCST) reached capacity constraints in August 1986 as a result of the additional water added from the reprocessing of the Regenerative Hold-Up Tank (RHUT) "A" (T-950A). To allow for future additions to the DRCST, a portion of the tank will' be drained to the A and B RHUT's, diluted and discharged to the retention basins for eventual discharge into the Hadselville Creek.

Transfer of the DRCST water will result in negligible exposure to plant personnel. The majority of the radioactivity associated with the DRCST water is low energy : which is not capable of penetrating the PVC piping. The water itself is below 0.1 mrem / hour on contact, and is not detectable on a arem/ hour scale.

The relets 9 of tritium via the RHUT's and retention basins is a reviewed pathway. Transfer of tritiated water is not prohibited by the USAR or Technical Specifications. The maximum possible uncontrolled release postulated for the operation of the temporary DRCST transfer system (5000 gallons based on a surveillance every half-hour) represents one-fiftieth of the total quantity of tritiated water whose release analyzed. A failure mode exists which could lead to a violation of 10 CFR Part 20, but a release off-site of 5000 gallons of 5 MPC (Maximum Permissible Concentration units) tritiated water would have a negligible impact on the plant'is ALARA release guidelines of 10 CFR Part 50, Appendix I. (Log Number 828, Revision 0)

, 4. Six procedures were rewritten, and a new one added to further improve the District':s overall compliance with 10 CFR Part 50, Appendix I, 10 CFR Part 20, Appendix B, and .

Technical Specifications 3.15, 3.17, and 4.21.

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AP.3 05-13, " Environmental Release of Liquid Radioactivity;" AP.310-1L, " Liquid Radioactive Releases Compliance with 10 CFR 20;" AP.310-2L, " Liquid Radioactive Releases Compliance with 10 CFR 50;" AP.310-3 L, " Liquid Radioactive Release Monitor Setpoint Calculation;"AP.3 06-V-13, " Lower Limit of Detection Count Time Determination;" and AP.306-III-H, " Liquid Systems" were all revised. A new administrative procedure, AP.310-2 LA, " Calculation of Cumulative Off-Site Dose form the Release of Liquid Effluents by Radiation Protection Personnel" was written.

The changes provide improved administrative controls on the release of radioactive liquids collected in the .

RHUT's, more conservative radiological bookkeeping methods, and an improved off-site dose calculation method for RHUT releases. The changes made are strictly procedural in nature recognizing the change described by Log 828 above, and provide the plant with improved administrative controls. The changes do not constitute a major change to the plant's radioactive waste treatment system, since physical plant modifications were not made.

(Log Number 844, Revision 0)

5. The District wrote SP.203.15A to verify the operability of the Decay Heat Removal System (DHR) Train "A."

SP.2 03.15A replaces SP.203.05A during cold shutdown.

SP.203.15A will not require SFV-25003 (Borated Water Storage Tank suction supply to ECCS Train "A" pumps) to be electrically operable. SP.203.15A will also not test i the 10 CFR Part 50, Appendix R isolation switches for SFV-25003 and P-261A. SFV-25003 is disabled electrically. SFV-25003 will be operated manually.

Since the plant is in Cold Shutdown, the " Appendix R" isolation switches required to reach cold Shutdown are not necessary.

This SP is only for the decay heat removal function of the DHS system when the RCS Tave is below 280<F, and therefore does not affect the Updated Safety Analysis Report. DHS will be tested for LPI operability per SP.203-05A as normally required prior to startup. (Log Number 854, Revision 0)

MAJOR ITEMS OF SAFETY RELATED MAINTENANCE

! 1. Continue decay heat system pipe support modification work for the DHS Train "B" line.

2. Continued Class 1 snubber testing and seal replacement

effort, including reinstallation of the Reactor Coolant Pump " super" snubbers.

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3. Tubing installation for EFIC continues on the "A" side vertical tubing in the Reactor Building. Conduit installation began on a two shift basis.

4. MOVATS testing of 36 Limitorque operated valves needed to support the DHS Train "A" outage on November 20, 1986 is in progress.

5. Trans America Delaval (TDI) Diesel Generator "A" (the new Train "A" diesel generator) work continued through October, resulting in a successful synchronization to the Northern California Power Grid for its first ten minute run on November 4, 1986.

6. Preventive maintenance of the 4KV "C" Bus was in progress.

7. The casing drain lines for both trains of DHS were replaced per ECN R-0498.

, i REFUELING INFORMATION REQUEST

1. Name of Facility Rancho Seco Unit 1

2. Scheduled date for next refueling shutdown: 09/15/88

3. Scheduled date for' restart following refueling: 01/15/89

4. Technical Specification change or'other license amendment required:

d) Chdnge to Rod Index vs Power Level Curve (TS 3.5.2) b) Charige to Core imbalance vs Power Level Curve (TS 3.5.2) c) Tilt Limits (TS 3.5.2)

5. Scheduled date(s) for submitting proposed licensing action: 03/15/88

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

7. Number of fuel assemblies:

a) In the core: 177 b) In the Spent Fuel Pool: 31 6

8. Present licensed spent fuel capacity: 1080

9. Projected date of the last refueling that can be discharged to the Spent Fuel Pool: 12/03/2001

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATL 10/31/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH October 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 da9 in the reporting month. Compute to the nearest whole megawatt.

l OPERATING DATA REPORT l

DOCKET NO. 50-312 DATE 10/31/86 )

COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes

• Corrected from

2. Reporting Period: October 1986 previous month

3. Licensed Thermal Power (MWt): 2.772

4. Nameplate Rating (Gross MWe): 963

5. Design Electrical Rating (Net MWe): 918

6. Maximum Dependable Capacity (Gross MWe): 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 MWe): 0

10. Reasons For Restrictions, If Any: NRC letter dated 12/26/85 This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 745 7.296 101.161

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) -3.065 -34.072 38.296.030 19, Unit Service Factor 0.0% 0.0% 49.8%

20. Unit Availability Factor 0.0% 0.0% 51.0%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 43.4%

22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 41.2%

23. Unit Forced Outage Rate 100.0% 100.0% 36.3% *

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 Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A __ N/A COMMERCIAL OPERATION N/A N/A l

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-312  ;

UNIT NAME Hancr:0 deco Unit 1

' DATE 10/31/86 COMPLETED BY R. Colombo REPORT MONTH October 1986 TELEP!!ONE 916/457-3711

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, j? 3 j .Eli Licensee ,E r, e, g'8 Cause & Corrective

%. Date g 3g s ,;; j 5 Event p gU Action to

$2 5 j ;f3 g Report # mO g Prevent Recurrence d

1 85/12/25 F 744 A 3 85-25 CB INSTRU RX TRIP FOLLOWING LOSS OF ICS POWER I 2 3 4 f Forced Reason: Method: Exhibit G Instructions S Scheduled A Equipment Failure (Explain) 1-Manua! for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source l'8/77) Il Other (Explain)

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5SMU= 'h SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-1830,(91 19452-3211 AN ELECTRIC SYSTEM SERVING THE HEAflT OF CALTQRNIA

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• RWC 86 674 November 14, 1986 I (

J B MARTIN REGIONAL ADMINISTRATOR (

REGION V OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUT CREEK, CA 94596

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OPERATING PLANT STATUS REPORT DOCKET NO. 50-312 Enclosed is the October 1986 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station pursuant to f Technical Specification 6.9.3. I WA R. W. COLOMBO l REGULATORY COMPLIANCE SUPERINTENDENT Encl (5) l cc: I&E Wash (12)

MIPC (2)

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

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