ML18101B049

Monthly Operating Rept for Sept 1995 for Salem Unit 1.W/ 951011 Ltr

ML18101B049
Person / Time
Site:	Salem
Issue date:	09/30/1995
From:	Heller R, Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510190067
Download: ML18101B049 (10)

Text

e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit October 11, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555.

Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMN0.1 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 September are being sent to you.

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 8-1-7.R4 The power is in your hands.

9510190067 950930 PDR ADOCK 05000272 95-2168 REV. 6/94 R PDR

AVERAGE DAILY UNIT POWER LEVEL

'1 e

Docket No.: 50-272 Unit Name: Salem #1 Date: 10/10/95 Completed by: Robert PhiTl.j:J)S Teleeh~!!e: 339-2735 Month September 1995 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 2~ 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 16 0 P *. 8 .1-7 Rl

'~

OPERATING DATA REPORT ~

Docket No: 50-272 Date: 10/10/95 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period September 1995

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 NA This Month Year to Date Cumulative

12. Hours in Reporting Period 720 6551 160008 12~ No. of Hrs. Rx. was Critical 0 2660.9 104380

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator on-Line 0 2632.1 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 8010326.4 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 2689850 105301000

18. Net Elec .. Energy Gen. (MWH) -3133 2529502 100211666

19. Unit Service Facto~ 0 40.2 62.7

20. Unit Availability Factor 0 40.2 62.7

21. Unit Capacity Factor (using MDC Net) 0 34.9 56.6

22. Unit Capacity Factor (using DER Net) 0 34.6 56.2

23. Unit Forced Outage Rate 26.7 56.3 22.9

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

Scheduled refueling outage.

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

Under review.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH: SEPTEMBER 1995 DOCKET NO.: 50-272 UNIT NAME: Salem #1 DATE: 10/10/95 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE

' DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1 2 NO. DATE  ! TYPE (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 2671 9-1-95 F 720 D 4 --------- SH CKTBRK Tech Spec. 3.0.3 e

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 (LER) 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: SEPTEMBER 1995 UNIT NAME: SALEM 1 DATE: 10/10/95 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)

The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.

2. Temporary Modifications (T-Mod)

T-Mod 95-058 "Installation of a Blind flange on 12SE72 Outlet Piping" - The purpose of this modification is to provide a secondary boundary for the leaking 12SW76 isolation valve. This temporary modification will add a blank flange in the 10" line 1-SW-P-1665 on the outlet pipe flange to the removed 12SW72 valve.

The supply and return line to Fan Coil Unit 1SWE25 (No. 12 Containment Fan Coil Unit) was isolated and tagged. The tagged valves are 12SE54, supply, and 12SW76, return. Valve 12SW72.was removed for maintenance. Valve 12SW76 will not fully isolate and leaks by. The leakage is being drained through drain valve 12SW425 with the water flow being directed to the floor drain. With the discharge header being placed back into service, the flow through the leaking valve will be too much for the floor drain to handle. Therefore it is necessary to install this blank flange. The blank flange is equivalent to a tagged closed valve. No new equipment configurations are introduced by this T-Mod. The Technical Specifications were reviewed and found to be not applicable for the current mode (undefined) and configuration. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-107)

IOCFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: SEPTEMBER I995 UNIT NAME: SALEM I DATE: 10/I0/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5I62 (Cont'd)

3. Procedures SI .MD-FR.ZZ-0003(Z) "Alternate Power Source for Cafeteria" Rev. 0 - The purpose of this procedure is to provide the instructions necessary to temporarily install power cables between 2HL (280/120 Volt Bus) and breaker IHIAY (output side). With breaker 2HL4Y closed and breaker IHL4Y open, power is provided to cafeteria power panels CPP I and CPP2 during #I I Station Power Transformer (SPT) outage or when 4I60 280/I20V Transformer IXFRIH3DAY is out of service. All equipment affected by the procedure is located within the turbine buildings (UI and U2). The IHL/2HL 208/120V AC busses do not supply any equipment important to safety nor do they affect any equipment important to safety. In addition, the loading on the alternate power source (2HL) will be limited to ensure overload/overcurrent conditions do not develop. The IHL/2HL

. 208/I20V AC busses are not covered by the Technical Specifications. Neither the busses nor the equipment supplied by the busses affect the margin of safety as defined in the bases of the Technical Specifications. (SORC 95-100)

Sl.MD-FR.230-000I(Q) "IF-IH 230 Volt Bus Crossfeed," Rev. 0 - This procedure provides the instructions necessary to install temporary power cables between IH 230 Volt group bus and IF 230 Volt group bus during respective Station Power Transformer (SPT) outages or 4I60-240/139V transformer outages. During I2SPT outage or 4160-240/139V Transformer lXFRlFSDBY outage, breaker lHY is closed and breaker lFY is open, resulting in IF 230 Volt bus being powered from lH 230 Volt bus. During I ISPT outage or 4160-240/139V Transformer IXFRIHSDBY outage, breaker IFY is closed and breaker lHY is open, resulting in lH 230 Volt bus being powered from IF 230 Volt bus. Busses lH and IF (230V AC group busses) are not covered by Technical Specifications. Neither the busses nor the equipment supplied by the busses affect the margin of safety as defined in the bases of the Technical Specifications.

(SORC 95-100)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: SEPTEMBER 1995 UNIT NAME: SALEM 1 DATE: 10/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 Security Procedure 9 "Control of Packages and Materials," Rev. 0 - The revision deletes the requirement for controlling personnel and material access to the primary reactor containment from within the adjacent vital area. Personnel access control will continue to be applied for access from the protected area to Salem's containments through the equipment hatches. The proposal involves no plant equipment and does not reduce the quality of oversight of the Security Program. There is no reference to the security control of primary reactor containment. There is no reduction in the margin of safety _as defined in the basis for any Technical Specification. (SORC 95-101)

Security Procedure SP7 "Personnel Access Control," Rev. 7 - Security Procedure SP7 is being revised in response to a change to the Federal Regulations

- deletion of 10CFR73.55(d)(8). This has eliminated the requirement for controlling personnel and material access to primary reactor containment from within an adjacent vital area.

Personnel access control will continue to be applied for access from the protected area to Salem's containments through the equipment hatches. The proposal involves no plant equipment and does not reduce the quality of oversight of the Security Program. There is no reference to the security control of primary reactor containment. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-110)

4. Updated Final Safety Analysis Report (UFSAR) Change Notice SCN 95-36 "Sections 17 .2.2 & Table 17.2-1 J .1.1 a" - The purpose of this submittal is to change the station's UFSAR by deleting the security program (administrative procedures) from the Q-List in Table 17.2.1, and reference to Regulatory Guide 1.17, Protection of Nuclear Plants Against Industrial Sabotage, (which has been revoked by the NRC) from Section 17.2.2.

Regulatory Guide 1.33 Appendix A cites Security & Visitor Control as activities that should be covered by written administrative procedures. There is no reference to the security

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: SEPTEMBER 1995 UNIT NAME: SALEM 1 DATE: 10/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 system. Quality requirements applicable to Security are contained in 10CFR73.55 and in the Security Plan (UFSAR Section 13.6). Therefore the Q-Listing of the Security Program is redundant. Its removal from the Q-List will have no effect on the quality or oversight of the Security Program. The proposal involves no plant equipment and does not reduce the quality of oversight of the Security Program. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-101)

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: SEPTEMBER 1995 UNIT NAME: SALEM 1 DATE: 10/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : SEPTEMBER 1995 .

Refueling information has changed from last month: YES X. NO _ _

Scheduled date for next refueling: 07/10/95 Scheduled date for restart following refueling: 1st quarter 1996

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 8-1-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 OCTOBER 1995 SALEMUNITNO. 1 The Unit is in a refueling outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units 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