ML18101B324

Monthly Operating Rept for March 1996 for Sngs Unit 1.W/ 960412 Ltr

ML18101B324
Person / Time
Site:	Salem
Issue date:	03/31/1996
From:	Heller R, Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604190105
Download: ML18101B324 (11)

Text

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• e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridg~. New Jersey 08038-0236 Nuclear Business Unit April 12, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: bocument Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 report for the month of February is being sent to you.

Sincerely yours,

~dJ7L/

C. Warren General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 9604190105 960331 PDR ADOCK 05000272 R PDR ,

The power is in your hands.

95-2168 REV. 6/94

OPERATING DATA REPORT Docket No: 50-272 Date: 04/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period March 1996

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 NA This Month Year to Date Cumulative

12. Hours in Reporting Period 744 2184 164401

12. No. of Hrs. Rx. was Critical 0 0 104380.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 0 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 0 105301000

18. Net Elec. Energy Gen. (MWH) -2207 -6844 100198069

19. Unit Service Factor 0 0 61.1

20. Unit Availability Factor 0 0 61.1

21. Unit Capacity Factor (using MDC Net) 0 0 55.1

22. Unit Capacity Factor (using DER Net) 0 0 54.7

23. Unit Forced Outage Rate 0 0 22.9

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

We are presently in a scheduled extension of a refueling outage.

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

Under review.

8-l-7.R2

AVERA- DAILY UNIT POWER LEVEL e Docket No.: 50-272 Unit Name: Salem #1 Date: 04/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month March 1996 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 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH March 1996 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 04/10/96 COMPLETED BY Robert Phillips TELEPHONE 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 3824 03-01-96 s 744 c 4 ---------- zz zzzz Schedule Extension of Refueling 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 Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MARCH 1996 UNIT NAME: SALEM 1 DATE: 04/10/96 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.

1. Design Change Packages (DCP) lEC-3323. Pkg. 2 "Service Water Large Bore Pipe Replacement" Rev. 2 - This DCP establishes an interim system configuration and boundaries without 13 SW20 to facilitate the restoration of the service water nuclear header No. 12. The system will be restored to original flow configuration by re-installing the refurbished 13 SW20 valve and the associated piping spools during a later header 12 outage with completion of service water DCP, IEC-3323, Pkg. 3, Rev. 1. The interim configuration, by replacing the turbine crosstie isolation valve with the blind flange, maintains the design basis and safety related function of the system. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-146) lEC-3424, Pkg 1 "Security System CCTV Tower Relocation/Elimination" Rev. 0 This DCP relocates the existing four cameras from the isolation zone to inside the protected area. Three new towers will be built with one tower having two cameras mounted on it. The Salem CCTV security systems and components are non-safety related and do not interface with any safety related systems or components. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 95-108) lEC-3428, Pkg 1 "Main Turbine Lube Oil (MTLO) Evactor Drain" Rev. 0 - This DCP modifies the piping to prevent oil from being discharged into the Delaware River and corrects problems with the existing drawings. The proposed changes will improve the operation of the MTLO Evactor system which will enhance the ability to maintain the LO Reservoir. The MTLO Evactor

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MARCH I996 UNIT NAME: SALEM I DATE: 04/I0/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5I62 Cont'd

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drain piping is not referenced in the Salem Unit I Technical Specifications or its bases and the proposed change does not impact margin of safety as defined in the bases.

(SORC 95-I54)

IEC-3429, Pkg. I "IA Emergency Diesel Generator (EDG) Jacket Water Piping Modification" Rev. I - This DCP adds a flexhose downstream of the isolation valve to isolate the tubing between the pressure switch and the isolation valve from the diesel generator vibrations. To accommodate the flexhose installation, tubing downstream of the flexhose will be rerouted and supported.

This will mitigate jacket water system instrument line vibrations, thereby increasing reliability and availability of the EDG. The modifications do not affect the load on the EDG, the output capacity, or the number of EDGs that are available for service.

Therefore, the proposed change will not reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-0I I)

IEC-3438, Pkg. I "IA Diesel Generator Circuit Breaker Voltage Permissive Relay Installation & Indication Modification" Rev. 0 - This DCP installs two new voltage sensing relays and an auxiliary relay to monitor the output voltage of Emergency Diesel Generator (EDG) IA. Contacts from the auxiliary relay will replace the existing voltage permissive contact (VSR) in the closing circuit for the Main Circuit Breaker on the EDG. The setpoints of the new voltage sensing relays are at a higher voltage than the existing relays and will ensure the EDG Main Circuit Breaker is only allowed to close when generator voltage is 9I % to 95% of rated voltage. The modifications performed by this DCP will improve system operation and will not prevent the IA EDG from operating in accordance with Technical Specification requirements. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-I48)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MARCH 1996 UNIT NAME: SALEM 1 DATE: 04/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 Cont'd

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lEC-3453, Pkg. 1 "Emergency Diesel Generator (EDG) lA Fuel Oil Day Tank Level Low Switch Setpoint Changes" Rev. 0 - The purpose of this design change package (DCP) is to raise the EDG lA Fuel Oil Day Tank low level alarm and back-up pump start setpoint from 18" to 27". This will provide at least 60 minutes ofEDG operation at the back-up pump auto refill level per ANSI N195-1976. The existing setpoint provides 41 minutes of operation (based on full load plus 10% or 2860 KW). The Technical Specification Bases were reviewed and do not explicitly define margin of safety relative to this DCP. However, this setpoint change is in the conservative direction so the margin of safety will be increased by this proposal. (SORC 96-008) lEC-3455, Pkg. 1 "Diesel Generator lA Prelube Oil Pipe Modifications" Rev. O -

This DCP modifies the piping between the Diesel Generator and the Oil Pump, and between the Prelube Oil Pump and the Oil Heater for Diesel Generator lA. Flexible mechanical joints and flexhoses will be installed on the suction and discharge sides of the Prelube-Oil Pump. Adapter plates will be installed between the Prelube Oil Pump and the diesel engine skid. The Prelube drain valves will be permanently removed. The installation of the flexhoses and flexmaster elbows on the Prelube Oil systems will mitigate the problems associated with the vibration of safety related components, increasing the reliability of the EDG.

These modifications do not affect any parameter of operation of the lube oil system. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-009) lEC-3529, Pkg. 1 "Emergency Diesel Generator (EDG) lA Modifications" Rev. 0

- This DCP increases the vibration tolerance characteristics of the lA Diesel Generator and associated equipment to harden the diesel against vibration related degradation. The installation of flexhose, clamping and bracing, and the strengthening of components susceptible to vibration, will mitigate the problems associated with the vibration of safety related components, increasing the reliability of the EDG. These modifications do not affect any parameter of operation of the lube oil systems.

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MARCH 1996 UNIT NAME: SALEM 1 DATE: 04/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-009) lEC-3540, Pkg. 2 "Safety Injection Pump Cross Over Motor Operated Valves (1lSJI13 And 12SJI 13) Disc Weep Holes" Rev. 0 - This DCP is to drill a 1/8" weep hole in the valve disc ( 11 SJI 14 valve side) of the Safety Injection Pump Cross Over Motor Operated Valves 11SJI13 and 12SJ113. This change is to provide an internal relief path to preclude potential pressure locking due to a pressure buildup in the valves' bonnet cavity and in the space between the valve discs. This is consistent with preventive methods promulgated in NUREG-1275, Vol. 9. The margin of safety as defined in the bases for the Technical Specifications is not affected. This modification will not reduce the safety margin of the Safety Injection System and will enhance the reliability of the system by providing an internal relief path for any fluid trapped in the valve bonnet, thus ensuring valve operability. (SORC 96-019)

2. Temporary Modifications (TMOD)96-002 "Temporary Relocation of the Operations Support Center (OSC) From The Control Room Corridor To The Service Building Corridor" - This temporary modification (TMOD) temporarily relocates the OSC to the Service Building corridor.

The distance between the locations is less than 50'. There is no impact in the ability of the OSC to assemble at the temporary location. The OSC communications lines will operate in the same manner in the temporary location. The installation of the temporary lines has no effect on any system/component addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-031)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MARCH 1996 UNIT NAME: SALEM 1 DATE: 04/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162

3. UFSAR Change Notices (SCN)

SCN 96-25 "Quality Assurance During The Operations Phase" - This change deletes from Section 17.2.11, "Test Control," the following, "System tests performed following modifications to Q Listed systems require review of test procedures and the test results by the SORC." There are no expected effects as there are no requirements in the current revision of the Technical Specifications for SORC to review these items. If a test procedure is part of a modification that requires a 10CFR50.59 evaluation, then SORC would review it as part of the modification. Evaluation of the test results and test data is the responsibility of the Test Engineer as defined in procedure NC.DE-AP.ZZ-0012(Q), Rev. 6. This change is administrative in nature and does not revise any operating point, analysis or setpoint of any equipment important to safety. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-034)

SCN 96-24 "Change of Diesel Generator Makeup Water From Automatic To Manual" - This change allows manually isolating makeup water to the Jacket Water Cooling System. Although the Jacket Water Cooling System Expansion Tank is still equipped with a ball float valve mounted inside the tank, the makeup water supply to the expansion tank is manually operated due to concerns associated with Expansion Tank overflow and spillage of hazardous chromated water. Establishment of this alignment for the system is expected to have no adverse effect on any system, structure or component important to safety. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-037)

L__

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: MARCH 1996 UNIT NAME: SALEM 1 DATE: 04/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : MARCH 1996 Refueling information has changed from last month: YES . X . NO ~*-~

Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: (to be determined)

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? (to be determined)

Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore 0

b. In Spent Fuel Storage 1005 Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632 Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008 8-l-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 MARCH 1996 SALEM UNIT NO. 1 The Unit is in a refueling outage and remained shutdown for the entire period. Evaluation and assessment of the Steam Generator tube indications continues. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the Unit will remain shutdown pending completion of the following actions:

• Appropriately address long standing equipment reliability and operability issues

• After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner

• After the restart review, meet with the NRC and communicate the results of that review