ML18100A945

Monthly Operating Rept for Feb 1994 for Salem Unit 1. W/940314 Ltr

ML18100A945
Person / Time
Site:	Salem
Issue date:	02/28/1994
From:	Hagan J, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403180083
Download: ML18100A945 (11)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 14, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of February 1994 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People ,,.---------- - - -- .

I 9403180083 940228 ------"]

ll '~DR ADOCK 0500~5~2

• 95-2189 (10M) 12-89

~ERAGE DAILY UNIT POWER LE~

Docket No.: 50-272 Unit Name: Salem #1 Date: 03/10/94 Completed by: Mike Morroni Telephone: 339-2122 Month February 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET} (MWe-NET) 1 0 17 0 2 25 18 0 3 440 19 0 4 2 20 233 5 29 21 972 6 511 22 1095 7 441 23 1128 8 549 24 1056 9 1068 25 777 10 498 26 852 11 0 27 1001 12 0 28 974 13 0 29 14 0 30 15 0 31 16 0 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 03/10/94 Completed by: Mike Morroni Telephone: 339-2122 Operating Status L Unit Name Salem No. 1 Notes

2. Reporting Period February 1994

3. .Licensed Thermal Power (MWt) 3411

4. Nameplate Rating (Gross MWe) 1170

5. Design Electrical Rating (Net MWe) 1115

6. Maximum Dependable Capacity(Gross MWe) 1149

7. Maximum Dependable Capacity (Net MWe) 1106

8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA

9. Power Level to Which Restricted, if any (Net MWe) N/A

10. Reasons for Restrictions, if any ~~~~~~~N::..:..i-=A=---~~~~~~~~~~~

This Month Year to Date Cumulative

12. Hours in Reporting Period 672 1416 146857

12. No. of Hrs. Rx. was Critical 612.03 730.23 95862.20

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 335.85 355.85 92243.69

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1896554.4 1903449.6 292682658.8

17. Gross Elec. Energy Generated (MWH) 292650 292650 96828620

18. Net Elec. Energy Gen. (MWH) 266572 248855 92168691

19. Unit Service Factor 53.0 25.1 62.8

20. Unit Availability Factor 53.0 25.1 62.8

21. Unit Capacity Factor (using MDC Net) 35.9 15.9 56.7

22. Unit Capacity Factor (using DER Net) 39.l 18.5 59.1

23. Unit Forced Outage Rate 43.5 43.5 21.1

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

None.

25. If shutdown at end of Report Period, Estimated* Date of Startup:

N A.

8-1-7.R2

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH FEBRUARY 1994 DOCKET NO.: -'5=0...,.-=27'-'2::..,.,..,.---

UNIT NAME: Salem #1 DATE: 03-10-94 COMPLETED BY: Mike Morroni TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0135 02/01/94 s 41.83 c 4 ------------ RC FUELXX NUCLEAR NORMAL REFUELING 0001 02/04/94 F 36.77 A 1 *----------- HF PUMP XX CIRCULATING YATER PUMPS 0002 02/10/94 F 237.57 A 3 ------------ HA TURBIN TURBINE ELECTRO/HYDRALIC CONTROL 0003 02/25/94 F 29.93 A 5 ------------ HF PUMP XX CIRCULATING YATER PUMPS 0006 02/25/94 F 29.93 A 5 ------------ HF PUMP XX CIRCULATING YATER PUMPS 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examin~tion Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

SAfETY RELATED MAINTEN,CE MONTH: *- FEBRUARY 1994 DOCKE~O:

UNIT NAME:

50-272 SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 WO NO UNIT EQUIPMENT IDENTIFICATION 920902207 1 VALVE 12MS131 FAILURE DESCRIPTION: BLOWING STEAM FROM BONNET -

REPLACE VALVE 931211085 1 VALVE 13SW92 FAILURE DESCRIPTION: VALVE ONLY STROKES 1/4 STROKE -

TROUBLESHOOT 940207127 1 RADIATION MONITOR 1R45 FAILURE DESCRIPTION: 1R45 CONTROL TERMINAL INOPERABLE

- INVESTIGATE 940211146 1 STEAM GENERATOR INLET HEADER PRESSURE INDICATION FAILURE DESCRIPTION: 1PI508 INDICATES HIGH -

TROUBLESHOOT 940213079 1 STEAM DUMP SYSTEM FAILURE DESCRIPTION: STEAM DUMP SYSTEM FAILURE -

INVESTIGATE 940218109 1 VALVE 1FT541 FAILURE DESCRIPTION: 14 S/G FLOW TRANSMITTER VALVE LEAKING - INVESTIGATE

-1 10CFR50.59 ~VALUATIONS~

MONTH:*- FEBRUARY 1994 DOCKEAO:

UNIT NAME:

50-272 SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The station Operations Review Committee has reviewed and concurs with these evaluations.

---

~-------------------------------------------------------

ITEM

SUMMARY

A. Design Change Packages lEE-0034 Pkg 1 "Circulating Water Standpipe Chlorination Salem Pump Installation" - The new design will consist of the following: 1.) Permanently Mounting three (3) new Masterflow Peristalis pumps on the existing support structure for the sample drain trough located inside the circulating water sample enclosure; 2.) Install 3 11 diameter PVC piping on the existing conduit support structure (additional pipe supports may be required) located behind the circulating water sample enclosure and branch off to each circulating water standpipe. The PVC pipe will be routed into the enclosure through the back wall; 3.) Run the 3/8 11 I.D. polyethylene pump suction tubing inside the 3 11 PVC piping from the circulating water standpipe into the sample enclosure. The proposed modification is being performed to enhance the reliability of the circulating water discharge chlorination monitqring system. This changes does not affect/change the total residual chlorine limits set forth by the NJPDES discharge permit. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-011) lEE-0027 Pkg 1 "Installation of Flowmeters for No. 13 Charging Pump Seal Water Tank Overflow Line" - This design change will install a turbine f lowmeter and digital flow totalizer on the No. 13 charging pump packing seal tank over flow line (3/4"-WL1125).

Presently No. 13 charging pump packing seal leakage from the seal water tank is classified as unidentified leakage. The flowmeter to be installed in the seal tank over flow line will be used to measure this leakage, therefore, pump seal leakage will be considered as identified leakage.

This modification does not affect the function of the No. 13 charging pump system, only the seal tank system which is not addressed in the

10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH:*- FEBRUARY 1994 UNIT NAME: SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

Technical Specifications. Therefore, this modification does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-011)

B. Technical Specification Interpretations (TSI)

T/S #3.7.4.1 "Operable Service Water Loop" - The purpose of this package is to support revision of the Salem Operations Technical Specification Interpretation for an Operable Service Water Loop (T/S Interpretation 3.7.4.1 for Salem Unit 1. The primary objectives of the revision are to update the interpretation(s) to more clearly address _the requirements for Service Water Loop operability and to correct an inconsistency which currently exists between the interpretation for Salem Unit 2 when compared to that of Unit 1. The proposed revision is more complete in that prior versions of this interpretation have tended to focus on the acceptable combinations of pumps and power buses.

The major changes to the revision are conservative enhancements that include specific identification of the acceptable combinations of pumps, valves, and piping which are required to provide operable Service Water loop(s). An additional change was made to remove a statement in regard to Technical Specification 3.0.5. The intent of this change is to eliminate confusion by permitting Technical Specification 3.0.5 to be the governing requirement. This TSI provides guidance consistent with the basis of the Technical Specifications. It does not alter the parameters of plant design or operation. This revision does not reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-014)

c. Temporary Modifications T-Mod 94-013 "Temporary Raw Water Pump" - This T-Mods installs a temporary pump in the Raw Water Storage Basin.

The pump is currently required to help maintain sufficient inventory of demineralized water (DM

• l~CF~50.59 'EVALUATIONS~ DOCKE,NO: 50-272 MONTH:*- FEBRUARY 1994 UNIT NAME: SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

water) in the DM storage tanks to allow continuous operation of the Salem plants in all modes of operation. This pump will supplement the raw water storage basin pump(s) already operating.

This T-Mod does not reduce the margin of safety as defined in the basis for any Technical Specification. It provides another pump at the raw water storage basin to help ensure that sufficient make-up is available to the DM plant so that sufficient inventory of DM water is available to the plant. The margin of safety in the plant is unaffected. (SORC 94-013)

T-Mod 93-123 "Double Valve At 1ST13 and 1ST21 for DCP 2EC-3187 11

- This temporary modification will hang temporary tags on two valves formerly identified as 1ST13 and 1ST21. This will allow the original valves to remain installed in the system. The valves will not be identified as 1ST13"t" and 1ST21"t". These valves were replaced by DCP 2EC-3187. The original valves are to be left in place because they are a boundary with Service Water as fed from Unit 1. This T-Mod will place the old valves in the open position. The new valves will be used for isolation. The old original valves will now be identified as 1ST13"T" and 1ST21"T" and tagged open. This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. The Technical Specifications have no applicability to service water in the Turbine Building. (SORC 94-016)

D. SAR Change Notices SCN 94-02 "Control Room Habitability Evaluations" - Sections 2.2.3 and 6.4 of the Salem UFSAR discuss control room habitability evaluations. There are two sources of hazardous chemicals that are required to be evaluated; onsite storage, and delivery and off- site traffic and delivery. This safety evaluation reviews the incorporation of data provided by the US Coast Guard in their July 1993 transmittal into the Salem UFSAR. This data is a compliance of barges transporting hazardous

. l~CF~50.59 'EVALUATIONS~ DOCKE~O:

UNIT NAME:

50-272 MONTH:*- FEBRUARY 1994 SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

chemicals past the Salem site. The frequency of the river barge traffic of each of the hazardous chemicals is considered "infrequent" according to position C-2 of Regulatory Guide 1.78. Therefore, further evaluation of a postulated release from a river barge transporting any of the hazardous chemicals is not required per Regulatory Guide 1.78. This proposal updates the SAR to reflect a recent evaluation of river traffic transporting hazardous chemicals past the site. The river traffic data concludes that the frequency of barges transporting hazardous chemicals past the site is "infrequent" according to Regulatory Guide 1.78. The probability of a chemical release from a river barge is not considered a credible accident, and therefore, does not require an evaluation for its impact to the EACS. Therefore, this proposal does not reduce the margin of safety as defined in the basis of any Technical Specification. (SORC 94-011)

SCN 93-07 "UFSAR Table 6.3 Refueling Water Storage Tank"

- The purpose of this change is to revise the code designation of the Refueling Water Storage Tank (RWST) in the UFSAR Table 6.3-1 from API 650 to ASME Section III, Class C. The SAR change is in response to DEF DES-92-00120 of the Safety Injection System CBD. This SAR change neither changes the plant design nor makes any new commitments. It simply corrects an error in the UFSAR regarding the code applicability of the RWST. There is no change to the design limits of the safety related systems or components. There is no reduction in the margin of safety as defined in the basis of any Technical Specification.

(SORC 94-018)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 FEBRUARY 1994 SALEM UNIT NO. 1 The Unit began the period operating at 47% power to perform reactor physics testing and nuclear instrument setpoint adjustments. The Unit was taken off line at 01:25 on February 4, 1994, due to problems with ice and grass buildup on the circulating water intake screens. The Unit was resynchronized at 14:10 on February 6, 1994, and increased to 47% power to continue reactor physics testing and instrument setpoint adjustments. The testing was completed and the Unit was returned to 100% power on February 10, 1994. Later, at 12:58 hours, the Unit tripped due to loss of 15 VDC electro-hydraulic control (EHC) power.

Startup was initiated and on February 15, 1994 the reactor achieved criticality. The Unit was then maintained critical at 10- 8 amps in the intermediate range while investigation into the loss of EHC control power continued. Investigation and subsequent testing was completed and the Unit was synchronized on February 20, 1994. Reactor power was increased to essentially 100% power on February 22, 1994.

With the exception of load reductions to clean circulator waterboxes and screens, the Unit continued to operate at essentially full power throughout the remainder of the period.

.RE;U~LING *TNFORMATION e DOCKE,NO: 50-272

~ MONTH: . - FEBRUARY 19 9 4 UNIT NAME: SALEM 1 DATE: MARCH 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH FEBRUARY 1994

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: MARCH 4, 1995

3. Scheduled date for restart following refueling: MAY 2~ 1995

4. a) Will Technical Specification changes or other license amendments be required?:

YES NO NOT DETERMINED TO DATE X b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES NO X If no, when is it scheduled?: MARCH 1995

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

N/A

6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 732

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-l-7.R4