NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station

Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station

ML20055F836
Person / Time
Site:	Rancho Seco
Issue date:	06/30/1990
From:	Delezenski J, Nagel R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NL-90-423, NUDOCS 9007190267
Download: ML20055F836 (8)

Text

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'Osuun SACRAMENTO MUNICIPAL UTluTY 068TR6CT D 6201 S Street, P.O. Box 16830, Sacramento CA 958621830.(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA NL 90-423 i

i July 16, 1990 i

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-U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hashington, DC 20555 l

Docket No. 50-312 Rancho Seco Nuclear Generating Station t

t.icense No. DPR-54 OPERATING PLANT STATUS REPORT Attention:

John Larkins Enclosed '.s the June 1990 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station.

The District submits this report pursuant to i

Technical Specification 6.9.3.

s Sincerely, f

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L Inry4elezenski Supervisor, Nuclear Licensing 4

Enci (5) cc w/ encl:- J. B. Martin, NRC, Halnut Creek A. D'Angelo. NRC, Rancho Seco R. Twilley, Jr.

ft k 9tioW 90267 900630 V

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1 ADOCK0500g2 DR

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- RANCHO SECO NUCLEAR GENERATINo STATION D 1444o Twin Cities Road, Herald, CA 95638 9799;(2o9)333-2935" P

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l MM SUM 4ARY OF PLANT CPERATIONS The plant has been in a defueled condition since the last of the fuel was removed and placed in the Spent fuel Pool at approximately 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on Friday, December 8,1989.

SUIMARY OF CHANGES IN ACCORDANCE MITH 10 CFR 50.59 The plant staff accepted documentation packages in June 1990 for the changes described below which required detailed safety analyses.

These changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).

1.

Layup package L-0067 Revision 0, for Diesel Generators was accepted.

The layup prevents autostart and load sequencing of the "B" Bruce GM and both TOI EDGS following undervoltage trip. USAR Sections 4.2.2.4. 8.2.3.3, 8.2.3.1.2.5, and 8.2.3.1.2.6 indicate each EDG will automatically start and pick up its respective 4KV bus on loss of voltage.

This modification will defeat the autostart but will not prevent the autoload shedding from the Nuclear Service Busses on loss of power.

This change has been analyzed against the two credible accidents and determined not to affect either loss of offsite power or fuel handling. There are no safety related loads required to be powered from the "B", "A2", or "B2" Nuclear Service bus. Therefore, equipment important to safety in the defueled condition is not affected by this change, nor is there any reduction to the margins of safety to operate the "A" Bruce Diesel independent of the diesels designated for layup.

2.

PDQ 90-0085, Revision 0, involved the detection of Co-60 and Cs-137 in the Circulating Hater Sludge Sample.

The detection of activity was slightly above background, and when evaluated against IE Bulletin 80-10, determined continued operaticn of the system was acceptable.

The determination concluded that previous analyses were bounding, and therefore, did not increase the probability of occurrence or consequences of an accident or. equipment malfunction.

There is not a possibility for an accident of a different type.

Therefore, to allow continued operation of the system does not involve an unreviewed safety question.

3.

Chemistry Administrative Procedure CAP-0014, Revision 1. "Long Term System Layup Chemistry Requirements", was revised to address plant layup requirements and conflicted with reactor coolant chemistry requirements as described in USAR Chapter 4.1.2.7, which requires boron concentrations for reactivity control.

Since the chemistry parameters for system layup will be different than those described i

during power operations, a reduction in the boron concentration I

requirements will provide corrosion control to mitigate system degradation during layup.

Therefore..this change to CAP-0014 does

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SUMARY OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 (Continued) 1 not increase the occurrence or consequences of an accident previously analyzed or malfunction of equipment previously l

analyzed.

Revision I to CAP-0014 does not involve an unreviewed safety question.

I 4.

Training Department Administrative Procedure TDAP-1010. Revision 2,

" Nuclear Training Area Organization" -was revised to change the

" Technical Staff Training" to " Licensing Training Program". The, administrative requirements for conduct of this program were transferred to each participating department and thereby decentralizing the training function; however, Nuclear Training will l

retain certain administrative responsibility for the program. The i

revision to TDAP-1010 does not increase the occurrence or consequences of an accident previously analyzed or the malfunction of equipment important to safety previously analyzed.

Revision 2 to TDAP-1010 does not involve an unreviewed. safety question, j

5.

Training Department Implementing Procedure TDIP-7090, Revision 0,

" Licensing Training Programd, was developed to support the change to TDAP-1010. Revision 2.

This procedure formalizcs the Licensing a

Training Program and assures perscnnel required to perform specific tasks are trained and qualified prior to the performance of the task. The new procedure, TDIP-7090, does not increase the occurrence or consequences of an accident or malfunction of equipment important to safety previously analyzed in the USAR.

Revision 0 to TDIP-7090 does not involve an unreviewed safety

question, i

6.

Training Department Administrative Procedure TDAP-1010, Revision 3,

" Nuclear Training Area Organization", was revised to delete the requirement for simulator training.

This change was precipitated via US NRC correspondence, dated May 16, 1990, which exempted Rancho l

Seco from the requirements to 10 CFR 55 regarding Simulator /

1 Simulator Training. The changes will result'in a change to the USAR, but do not itivolve an unreviewed safety question as demonstrated by the granted exemption.-

7.

Training Department Implementing Procedures TDIP-7080 Revision 1,

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" Conduct of Simulator Training"; T0!P-7050, Revision 2, " Licensed Operator Requalification Training Program"; TDIP-7040, Revision 2

" Senior Reactor Operator Training Program"; DIP-7130, " Reactor.

Operator Training Program"; and TDAP-1050, Revision 1. " Examination Control & Administration" were revised as a result of US NRC.

correspondence, dated May 16, 1990, which exempted Rancho Seco from the requirements of 10 CFR 55 regarding Simulator /Simulatsr i

Training.

The changes will result in s change to the USAR, but do

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not involve an unreviewed safety question as demonstrated by the granted exemption.

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SLM ERY OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 (Continued) 8.

Design Change Package (DCP) R90-0008, " Underground Tank Upgrade" was for compliance as a result of a revision to Chapter 6.7 of Division 20 of the California Health & Safety Code, This change results in the removal of leaded gasoline storage tank T-922; replacement of microwave diesel storage tank T-917 with an above ground tank; addition of an automatic leak detection for underground ortssurized piping for Security Diesel Tanks T-903A/8; and relocation of Hypochlorite Tank T-974.- The changes as a result of this DCP are plant betterments and do not increase the occurrence or consequences of an accident or malfunction of equipment important to safety previously analyzed in the USAR.

This change as a result of DCP R90-0008 does not involve an unreviewed safety question.

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-a.

s REFUELING INFORMATION REQUEST 1.

Name of Facility Rantho Seco 2.

Scheduled date for next refueling shutdown:

3.

Scheduled date for restart following refueling:

4.

Technical Specification change or other license amendment required:

1 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:

0 b)

In the Spent fuel Pool:

493 8.

Present licensed spent fuel capacity:

1080; 9.

. Projected date of the last refueling that can be discharged to the Spent Fuel Pool:

All fuel removed from the core as of December 8. 1989.*

• Plant shut down June 7,1989 following negative outcome of public vote i

.regarding contir.Jed operation of Rancho $eco by SMUD.

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r AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.

50-312 UNIT Rancho Secn DATE 6/30/90 i

COMPLETED BY R. E. Nagej TELEPHONE-(916) 452-3211 MONTH June 1 6 0 DAY.

AVERAGE DAILY POWEW LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MHe-Net)

P 1

0 17 0

2 0

18 0

l 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

t 14 0

30 0

15 0

31 16 0

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net lfor each day in the reporting month.

Compute to the nearest whole megawatt.

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t OPERATING DATA REPORT DOCKET NO.

50-312 i

DATE 6/30/90 l

COMPLETED BY MRIla Mueller TELEPHONE (916) 452-3211 OPERATING STATUS 1.

Unit Name:

Rancho Seco

%s;

-2.

Reporting Period:

June 1990 3.

Licensed Thermal Power (MHt):

2.772 i

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Nameplate Rating (Gross MHe):

963 i

5.

Design Electrical Rating (Net MHe):

918 6.

Maximum Dependable Capacity _(Gross MHe):

917 7.

Maximum Dependable Capacity (Net MHe):

873 8.

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

N/A 9.

Power Level to Mbich Rtstricted, If Any (Net MHe):

N/A i

10.

Reasons for Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative l

11, Hours in Reporting Period 719-4.342

_133.270 l

12.

Number of Hours Reactor Has Critical 0

0

._6L221. 5 13.

Reactor Reserve Shutdown Hours 0

0 12.736.6

14. Hours Generator On-Line 0

0 57.811.1

15. Unit Reserve Shutdown Hours 0

0 3.647.5

16. Gross Thermal Energy Generated (MHH) 0 0

141.951 953

17. Gross Electrical Energy Generated (MHH) 0 0

46.223.924

18. Net Electrical Energy Generated (MHH)

-3.023

-21.125

.42.443.180

19. Unit Service Factor 0%

01 43.9%

20. Unit Availability factor 0%

01 46.6%

21.

Unit Capacity Factor (Using MDC Net) 0%

01 36.91

22. Unit Capacity Factor (Using DER Net) 01 01 35.1%

23. Unit Forced Outage Rate 01 01 42.7%

24.

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

25.

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

i 26.

Units In Test Status (Prior to Commercial Operation):-

Forecast Achieved t

INITIAL CRITICALITY N/A N/A INITIAL' ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

• Plant. shut down June 7 following negative outcome of public vote regarding

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-continued operation of Rancho Seco by SMUD.

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15 TIT SRITDOWNS AND POWER REBUCIiONS 300ET15. - _58-312 ISIET IWWE shA, __

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ESTE 4-38-90 REPORT 951mt June 1998 COIR ETED WF R. E. IIeuel _

TELERWIE (916) 6 2-3211 Method of Shutting Licensee Cause & Corrective Duration Down Event System Component Action to No.

Date Type (Hours)

Reason 2 Reactor 3 Report #

Code Code 5 Preveet Reevrrence l

4 1

06-07-89 5

719 F

1 N/A N/A N/A Plant shut down June 7.15J9 following negative outcome of public vote regarding continued operation of Rancho Seco by SPUD.

1 2

3 4

F Forced Reason:

Method:

Exhibit G - Instrwetions S Scheduled.

A-Equipment Failure (Explain) 1-Manual for Preparation of Data Entry 8-Maintenance or Test 2-Manual Scram Sheets for Licensee Event C-Refvaling 3 Automatic Scram Report (LER) File (IRfREC--0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & License examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source H-Other (Explain)

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