ML18102A467

Monthly Operating Rept for Sept 1996 for Salem Unit 2

ML18102A467
Person / Time
Site:	Salem
Issue date:	09/30/1996
From:	Garchow D, Heller R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9610220204
Download: ML18102A467 (9)

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~.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTfil Y OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 October 14,1996 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 September is being sent to you.

RH:vls Enclosures C

Mr. H. J. Miller Sincerely yours;

\\~lJ~j David F. Garchow General Manager -

Salem Operations Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 9610220204* 960930 PDR ADOCK 05000311 R

PDR The power is in your hands.

95-2168 REV. 6/94

OPERATING DATA REPORT ~

Docket No:

50-311 Date:

10/10/96 Completed by:

Robert Phillips Telephone:

339-2735 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period September 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.~~~~~----'N~A=--~~~~~~~~~~~~~~~~~~~

9.

Power Level to Which Restricted, if any (Net MWe)

N/A

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

11. Hours in Reporting Period

12. No. of Hrs. Rx. was Critical

13. Reactor Reserve Shutdown Hrs.

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Elec. Energy Generated (MWH)

18. Net Elec. Energy Gen. (MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit capacity Factor (using MDC Net)

22. Unit Capacity Factor (using DER Net)

23. Unit Forced Outage Rate This Month 720 0

0 0

0 0

0

-3494 0

0 0

0 100 Year to Date cumulative 6575 131208 0

78083.6 0

0 0

75229.5 0

0 0

187781005 0

78648898

-28006 74713048 0

57.3 0

57.3 0

51.4 0

51.1 100 29.2

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

Refueling extension.

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

Under review.

8-l-7.R2

~ERAGE DAILY UNIT POWER LE~

Docket No.:

Unit Name:

Date:

50-311 Salem #2 10/10/96 Completed by:

Robert Phillips Telephone:

339-2735 Month September 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 16 0

P. 8.1-7 Rl

NO.

DATE 3859 09-01-96 1

F:

Forced S:

Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH Septeaber 1996 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE1 (HOURS)

REASON2 REACTOR REPORT #

COOE4 F

720 F.C 4

zz 2

3 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F*Acininistrative G-Operational Error (Explain)

H*Other (Explain)

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE5 DOCKET NO.:

_.5~0..,..-3-..1...,1-,,:--

UNIT NAME:

Salem #2 DATE:

10* 10-96 COMPLETED BY:

Robert Phillips TELEPHONE:

609-339**2735 CAUSE AND CORRECTIVE ACTl.ON TO PREVENT RECURRENCE zzzz Refuelfng Schedule Exceeded 4

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 - Same Source

10CFR50.59 EVALUATIONS MONTH: SEPTEl\\.IBER 1996 DOCKET NO:

UNIT NAME:

50-311 SALEM2 R.HELLER 609-339-5162 CONTACT:

TELEPHONE:

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) 2EC-3453, Pkg. 1 2EC-3467, Pkg. 3 2EC-3521, Pkg. 1 "Mid-Loop Wide Range Level Upgrade" Rev. 0 - This DCP installed a new differential pressure transmitter, toggle switch and indicator for wide range mid-loop level operations. There is no reduction in the margin of safety as described in the basis for any Technical Specification.

(SORC 96-089)

"Safety Injection System Motor Operated Valves 2SJ12 and 13 Disc Weep Hole Modifications (Generic Letter 95-07 Pressure Locking) Rev. 0 - This DCP drilled a 1/8" weep hole in the valve disc (charging pump/Boron Injection Tanlc side) of the Boron Injection Outlet to Cold Leg Valves 2SJ12 and 2SJ13. This provides an internal relief path to preclude potential pressure locking due to a pressure build up in the valves' bonnet cavity and in the spaces between the valve discs. This is consistent with preventive methods promulgated in NUREG-1275, Vol. 9. This modification enhances the reliability of the system. There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 96-051)

"Make Fuel Handling Building (FHB) Air Probe Installation Permanent" Rev. 0 - This DCP made minor changes to the hardware installed under Temporary Modification 95-066 in order to make the design permanent. The hardware changes are separation of the instrument sensing lines, new drip legs, improved lighting protection, and change out of the differential pressure switch to one with tamper resistant setpoint adjustments. This modification stabilizes the alarm and FHB ventilation control system, further ensuring that a negative pressure is maintained in the FHB, and that any

10CFR50.59 EVALUATIONS MONTH: SEPTEMBER 1996 DOCKET NO:

UNIT NAME:

50-311 SALEM2 R.HELLER 609-339-5162 2EC-3541, Pkg. 1 2EC-3560, Pkg. 1 CONTACT:

TELEPHONE:

released radioactive material will be filtered through the HEP A filters and charcoal absorber prior to discharge to the atmosphere. There is no reduction in the margin of safety as described in the basis for any Technical Specification.

(SORC 96-054)

"Letdown Isolation Bypass" Rev. 0 - This DCP installed a keylock switch, two auxiliary relays and one interposing relay. When the keylock switch is placed in the "bypass" position, the two auxiliary relays and an interposing relay will be energized. A contact from the interposing relay will energize the control console bezel letdown isolation bypass indicator light. The remaining contacts on the energized auxiliary relays will provide the correct contact configuration in order to allow the operator to bypass the low pressurizer level (less than 17% pressurizer level) isolation signal and allow positioning control for Chemical and Volume Control letdown valves. There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 96-081)

"Rework Sensing Line, Pressure Transmitter 2PT942" Rev.

0 - This DCP replaced the existing capillary filled tubing system in the sensing line for 2PT942, Boron Injection Tank discharge pressure transmitter located in Panel 215-2. The capillary system was replaced with at 3/8" stainless steel instrument line and associated valves. Also, the terminal block in Panel 215-2 where the transmitter output cable is terminated was replaced with an environmentally qualified splice. The instrument loop performs no control function and does not inhibit the required operation of the safety injection system. There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 96-083)

10CFR50.59 EVALUATIONS MONTH: SEPTEMBER 1996 DOCKET NO:

UNIT NAME:

50-311 SALEM2 CONTACT:

TELEPHONE:

2. Procedures and Revisions R. HELLER 609-339-5162 TS2.0P-PT.CVC-0002(Q)

"Troubleshooting on 21or22 Charging Pump with Temporary Modification of Plant Configuration" Rev. 0 -

This procedure provides the instructions necessary to obtain data for determining the flow chara~teristics of 21 and/or 22 Centrifugal Charging Pumps. The data is used for generating their respective pump performance curves that serve as baseline data. This information is useful when monitoring pump performance during the plant cycle and subsequent surveillance test requirements. There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 96-130)

3. UFSAR Change Notice (SCN)

SCN96-153 "Residual Heat Removal (RHR) Suction Piping Pressurization Issue" - FSAR Table 5.5-1 indicates RHR suction pressure is 450 psig. This needs to be revised to indicate that the portion of the suction piping between 2RH75 and 76 has a design pressure of 600 psig consistent with the pump discharge piping. The proposed change does not impact any system operational parameter but involves revising the design pressure for a portion of RHR suction piping discussed earlier. As such, no procedure changes are required to any procedure described in the SAR. There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 96-130)

.-----------------~-~--------------

~.

REFUELING INFORMATION MONTH: SEPTEMBER 1996 MONTH: SEPTEMBER 1996 DOCKET NO:

UNIT NAME:

CONTACT:

TELEPHONE:

50-311 SALEM2 R.HELLER 609-339-5162

1. Refueling information has changed from last month: YES ~* -~* NO. X.

2. Scheduled date for next refueling: (currently in refueling)

Scheduled date for restart following refueling: (to be determined)

3. 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)

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 0

b. In Spent Fuel Storage 777

8. Present licensed spent fuel storage capacity:

1632 Future spent fuel storage capacity:

1632

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

March 2012

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 SEPTEMBER 1996 SALEM UNIT NO. 2 The Unit remained shutdown for the entire period. 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