ML18095A200

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Monthly Operating Rept for Apr 1990 for Salem Unit 1.W/ 900511 Ltr
ML18095A200
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/30/1990
From: Miller L, Orticelle A
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005180058
Download: ML18095A200 (9)
v • d • e


Text

e OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 11, 1990 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 April 1990 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours,

le~

L. K. Miller General Manager -

Salem Operations RH:pc cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People 95-2189 (11M)12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date 05-10-90 Completed by Art Orticelle Telephone 609-339-2122 Month APRIL, 1990 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 7 122 23 0 8 890 24 0 9 587 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 16 0 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 05-10-90 Completed by: Art Orticelle Telephone: 609-339-2122 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period April 1990
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 N/A
9. Power Level to Which Restricted, if any (Net MWe) N/A

--~~'-"------------

10. Reasons for Restrictions, if any --=-N'-'-/--=-A=----------------------

This Month Year to Date Cumulative

11. Hours in Reporting Period 719 2879 112512
12. No. of Hrs. Reactor was Critical 108.68 2162.68 73071.23
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 48.87 2102.79 70798.55
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 134088.0 6892562.4 221993488.4
17. Gross Elec. Energy Generated (MWH) 41440 2290760 73752120
18. Net Elec. Energy Generated (MWH) 26313 2203218 70214928
19. Unit Service Factor 6.8 73.0 62.9
20. Unit Availability Factor 6.8 73.0 62.9
21. Unit Capacity Factor (using MDC Net) 3.3 69.2 56.4
22. Unit Capacity Factor (using DER Net) 3.3 68.6 56.0
23. Unit Forced Outage Rate 93.2 27.0 21.6
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Unit #1 Eighth Refueling scheduled on October 6, 1990 and lasting 45 da s.

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

Estimated start-up date of May 11, 1990.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS OOCKEI' NO.: --'5'--"0--'-2"'--'7~2_ _ __

REFDRI' MONTH APRIL

--- 1990

UNIT NAME: Salem #1 DATE: 05-10-90 COMPLEI'ED BY: Art Orticelle TELEPHONE: 339-2122 MEI'HOD OF SHUITING LICENSE DURATION OOWN EVENT SYSTEN CD.'1PONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS} REASON 2 REACIDR REFDRI' # CODE 4 CODE 5 'ID PREVENT RECURRENCE 0033 4-01-90 F 262.8 A 4 ---- IB INSTRU 1A S.E.C. 0035 4-09-90 F 513.5 A 3 ---- CH INSTRU #12 S.G. FEED PUMP I

I I I I I 1 2 3 4 5 F: Forced Reason: Method: Exhibit G - Instrnctions Exhibit 1 - Same S: Scheduled A-Equillll8nt 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 (LER) File D-Regulatory Restriction 4-Continuation of (NUREG-0161)

E--Operator Training &Lic-ense Examination Previous outage F-Admi.llistrative 5-1.oad Reduction G--Operational Error (&'Plain) 9-0ther H-Other (Ex-plain)

MAJOR ~LANT MODIFICATIONS DOCKET NO: 50-272 MdNTH: - APRIL 1990 UNIT NAME: SALEM 1 DATE: MAY 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068

  • DCR PRINCIPAL SYSTEM DESCRIPTION lEC-02245 Reactor Coolant This design change replaced the 1/4 Reactor Coolant Pump (RCP} Breaker Open Anticipatory Trip signal above P-8 with a 2/4 RCP Breaker Open Anticipatory trip signal above P-7.

1EC-02251A Smoke Detection This design change installed additional smoke detection equipment to various zones of the Auxiliary Building.

lSC-2092 Residual Heat This design change modified the Removal control circuits for Valves RHl and RH2 to delete the auto closure interlock feature.

  • Design Change Request

MiJ6R PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - APRIL 1990 UNIT NAME: SALEM 1 DATE: MAY 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068

  • DCR SAFETY EVALUATION 10 CFR 50.59 lEC-02245 This design change replaced the 1/4 Reactor Coolant Pump (RCP) Breaker Open Anticipatory Trip signal above P-8 with a 2/4 RCP Breaker Open Anticipatory trip signal above P-7.

This design change reduces the potential for inadvertent Rx trips and challenges to the Reactor Protection System.

There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

1EC-02251A This design change installed additional smoke detection equipment to various zones of the Auxiliary Building. This provides additional coverage of equipment areas by the automatic detection system. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lSC-2092 This design change modified the control circuits for Valves RHl and RH2 to delete the auto closure interlock feature.

Elimination of this feature reduced the potential for inadvertant actuation of these valves and brought the system design in conformance with current requirements.

There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request I

I I

_ _ _ _ _ _ _ _ _J

S~F~TY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - APRIL 1990 UNIT NAME: SALEM 1 DATE: MAY 10, 1990 COMPLETED BY: M. MORRON!

TELEPHONE: (609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 890804101 1 13 SERVICE WATER PUMP FAILURE DESCRIPTION: REMOVE AND REPLACE WITH SPARE PUMP 900104080 1 12 SAFETY INJECTION PUMP FLOW ORIFICE FAILURE DESCRIPTION: ORIFICE FLANGE LEAKING - REPLACE GASKET 900309121 1 11SW127 FAILURE DESCRIPTION: NO AUTO CONTROL - TROUBLESHOOT 900321100 1 14 SWITCHGEAR FAILURE DESCRIPTION: EXHAUST FAN STOP INDICATION DOES NOT LIGHT - TROUBLESHOOT 900402122 1 15 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: INDICATION PEGS AT LOW SPEED -

TROUBLESHOOT 900419103 1 #1 MAIN TRANSFORMER FAILURE DESCRIPTION: TROUBLESHOOT GEOMAGNETIC INDUCTION COUNTERS

I I

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 APRIL 1990 SALEM UNIT NO. 1 The Unit entered the period shutdown for repairs to lA Safeguards Equipment Cabinet (SEC). Following repairs to the SEC, delays were encountered during heatup due to leakage from an Emergency Core Cooling System (ECCS) check valve. The valve was reseated and the Unit was restored to approximately 91% power on April 7, 1990. The Unit continued to operate at that level until April 9, 1990, when the reactor tripped following separation of the linkage on 12 Steam Generator Feed Pump which resulted in a low water level in 12 Steam Generator. The Unit remained shutdown through the rest of the period for ECCS full flow testing and correction of identified concerns.

R~FUELING INFORMATION DOCKET NO: 50-272 MONTH: - APRIL 1990 UNIT NAME: SALEM 1 DATE: MAY 10, 1990 COMPLETED BY: M. MORRON!

TELEPHONE: (609) 339-2068 MONTH APRIL 1990

1. Refueling information has changed from last month:

YES NO x

2. Scheduled date for next refueling: October 6, 1990
3. Scheduled date for restart following refueling: November 19, 1990
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?: September 1990

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 540
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
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