ML18102A562

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Monthly Operating Rept for Oct 1996 for Salem Generating Station,Unit 2.W/961114 Ltr
ML18102A562
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/31/1996
From: Garchow D, Heller R, Phillips R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9611260012
Download: ML18102A562 (12)
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Text

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

Sincerely yours, Udrt,f,

'IJ:~;d F. Garchow General Manager -

Salem Operations RH:vls Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 9611260012 961031 PDR ADOCK 05000311 R PDR 250066 The power is in your hands.

95-2168 REV. 6/94 L

~ERAGE DAILY UNIT POWER LE~

Docket No.: 50-311 Unit Name: Salem #2 Date: 11/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month October 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

OPERATING DATA REPORT ~

Docket No: 50-311 Date: 11/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period October 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 ~~~~---=N~A~~~~~~~~~~~~~~

This Month Year to Date cumulative

11. Hours in Reporting Period 745 7320 131953
12. No. of Hrs. Rx. was Critical 0 0 78083. 6 '
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 187781005
17. Gross Elec. Energy Generated (MWH) 0 0 78648898
18. Net Elec. Energy Gen. (MWH) -3334 -31340 74709714
19. Unit Service Factor 0 0 57.0
20. Unit Availability Factor 0 0 57.0
21. Unit Capacity Factor (using MDC Net) 0 0 51.2
22. Unit Capacity Factor (using DER Net) 0 0 50.8
23. Unit Forced Outage Rate 100 100 29.6
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.

8-1-7.R2

I-UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH October 1996 DOCKET NO.: _5'-0'--~3~1~1_ _ __

UNIT NAME: Salem #2 DATE: 11-10-96 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 3859 10/01/96 F 745 FC 4 ---------- zz zzzz Refueling Scheduled Extension 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-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction *4-Continuation of CNUREG-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: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: 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) 2EC-3191, Pkg. 1 "Auxiliary Feedwater (AFW) Flow Reduction 21 - 24AF11 and 21 - 24AF21 Valve Modifications" Rev. 2 - This DCP eliminated full/throttled flow test requirements to revalidate the valve flow coefficients (Cv's) for control valves 21 through 24AF11and21through24AF21, due to the valve trim replacements performed under this DCP. The replacement valve trims were sized to produce the required Cv values using a Salem retran flow model which was validated through previous full flow testing. The manufacturer (Masoneilan) produced the required flow coefficients Cv' s via full scale laboratory flow tests. The vendor certified Cv curves have been incorporated into this DCP. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-140) 2EC-3260, Pkg.1 "Steam Generator (S/G) Blowdown System Upgrade Project" Rev. 1 - This DCP replaced the existing 21/22/23/24GB9, 23/24GB189, 21/22/23/24GB185, 21/22/23/24GB923, & 21/22/23/24GB924 with improved valves. The 21GB189 and 22GB 189 valves do not require replacement, because they have already been replaced with the same type valves. The GB9 valves were relocated to provide better accessibility. This portion of the Steam Generator Blowdown system is non-safety related. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-037) 2EC-3309, Pkg. 1 "Service Water Large Bore Pipe Replacement" Rev. 0 -

This DCP replaced the existing service water piping with 6% molybdenum stainless steel. These modifications

10CFR50.59 EVALUATIONS DOCKET NO: 50-3 I I MONTH: OCTOBER I996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5I62 upgraded the pipe material from cement or epoxy lined carbon steel to 6% molybdenum austenitic stainless steel.

The new material provides superior corrosion resistance relative to the existing material. The piping material, fabrication, installation and configuration has been designed to meet or exceed the original design basis. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-00I) 2EC-3363, Pkg. I "28 VDC Circuit Breaker Replacement" Rev. 0 - This DCP provided replacement of existing high resistance 28 VDC circuit breakers with larger capacity breakers. These breakers have a significantly smaller internal resistance which reduces voltage drop and improves reliability. The replacement components enhance the reliability of the circuits and do not affect their operation. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC-96-036) 2EC-3372, Pkg. 2 "Radiation Monitoring System (RMS) "Meteorological (MET) Package" Replacement" Rev. I - This DCP replaced the "MET Package" with two redundant processors. The MET package interfaces the RMS computers with the RMS annunciators on 2RP 1. This revision added a warning alarm for the RI 5 monitor. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-098) 2EC-3396, Pkg. I, "Installation of Transfer Switches for Appendix R Alternate Shutdown" Rev. 0 - This DCP replaced Motor Control Center (MCC) and control panel circuits for 36 components (3 chillers, I 7 valves, 4 vent fans, 8 room coolers and 4 pumps) were modified to include local switches which isolate component wiring from the Control Room, Relay Room and ceiling area of the 460-230 _Switchgear Room, thus precluding the necessity of electrical wiring modifications and jumpers to operate the subject equipment

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 in achieving Hot Standby (HSB) in the event of a fire in these areas. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-046) 2EC-3423, Pkg. 1 "Auxiliary Building Ventilation System (ABVS)

HEP A/Charcoal Filter Damper Fail Position Modifications" Rev. 0 - This DCP provides two new functions for the Salem Unit 2 ABVS: 1) revised the electric power fail safe position of ABVS dampers 2AVB2, 2ABV3, 2ABV6, 2ABV9 and 2ABV12 to comply with charcoal filter #24*

Technical Specification flow rates, and 2) provided an alternate means to ensure the charcoal filter unit #24 parallel outlet dampers 2ABV11and2ABV21 remain in the open position should a failure of the single solenoid valve 2SV800 occur. The revised loss of power failure modes and new bypass valves do not affect the capability of the ABVS from performing its safety function. No changes were made to any limiting conditions for operation. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-076) 2EC-3461, Pkg. 1 "Cavitation Mitigation on Safety Injection Cold Legs and Hot Legs" ~ev. 0 - This DCP replaced an approximate 4 foot length of2 inch piping in each Safety Injection (SI) branch line to the Reactor Coolant System (RCS) loop cold legs inside the containment with a pre-fabricated 2 inch pipe section consisting of six orifices in series. The new orifice section is installed immediately downstream of the 21-24SJi 44 check valves. The DCP also added orifices in the 2 inch piping in the SI branch lines to the RCS hot legs inside containment, immediately downstream of the 2 l-24SJ139 check valves. The design has been analyzed in this DCP by a flow calculation which concludes that the SI flow delivery requirements of Technical Specification (TS) 3/4.5, Surveillance Requirement 4.5.2h are met for the SI cold legs and hot legs. The Bases for TS 3/4.5.2 and 3/4.5.3 (ECCS Subsystems) for operability are met because the safety

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 analyses assumptions with respect to system resistance, branch line resistance, maximum and minimum flows (total flow and individual lines) and pump runout bound the valves as calculated and tested in this DCP. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-047) 2EC-3506, Pkg. 1 "Turbo-boost LP Alarm" Rev. 0 - This DCP revised the setpoint for emergency diesel generators 2A/2B/2C turbo boost air receiver low pressure alarms. This modification is necessary to: 1.) minimize spurious turbo boost alarms: 2.)

ensure adequate margin exists to allow for operator response, and 3.) establish a design basis for the alarm. This DCP increased the availability to the turho boost system by providing an earlier warning of low air receiver pressure and provides additional assurance that the emergency diesel generator will start and accept load to mitigate accident consequences. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-051) 2EC-3521, Pkg. 1 "Make Fuel Handling Building (FHB) Air Probe Installation Permanent" Rev. 0 - This DCP made minor changes to the hardware installed under Temporary Modification (TMOD)95-066 in order to make the design permanent. The TMOD was closed. The hardware changes are separation of the instrument sensing lines, new drip legs, improved lighting protection, and change out of the DP 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 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 defined in the basis for any Technical Specification. (SORC 96-054)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 2EC-3549, Pkg. 1 "Debris Mitigation on Charging/Safety Injection Cold Legs" Rev. 0 - This DCP added flow resistance orifices to each of the four Charging/Safety Injection (C/SI) System cold legs upstream of the flow elements and throttling valves 21SJI6, 22SJ16, 23SJ16, and 24SJ16. A length of the 1 1/2 inch C/SI cold leg piping inside the containment adjacent to the outside of the biological shield was cut out and replaced with a 1 1/2 inch pipe section (fabricated on-site) with orifices in series. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-054) 2EC-3581, Pkg. 1 "Manual Isolation of Containment Purge" Rev. 0 - This DCP split the functions of the existing "O A and Cont Vent Isolation Operate" pushbuttons (one per Train) on control board Section 2CC1 into two pushbuttons such that individual initiation of 0 A Isolation and Containment Ventilation Isolation is possible. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-109) 2EE-O 196, Pkg. 1 "Condensate and Main Steam System Chemical Injection/Sample Internal Sparger Pipe Removal" Rev. 0 -

This DCP removes selected chemical injection and sample spargers at various locations within the main steam and condensate system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-089)

2. Safety Evaluations PR 951017158 "Operability ofEDGs without Jacket Water After Cooler Heater" - This safety evaluation corrects the present description in the UFSAR for the function of the Salem emergency diesel generator (EDG) aftercooler heater (A-CH). The function of the A-CH is not related to the safe operation of the Diesel Generator. Section 9.4.5.3, "Design Evaluation - Diesel Generator Area Ventilation," states that

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: -609-339-5162 heaters are provided in the aftercooler Lube Oil System, and in the Jacket Water Cooling System to assure each diesel generator is maintained at a temperature at which it can be started in 10 seconds. Section 9.5.5, "Diesel Generator Jacket Water Cooling System," of the Salem UFSAR states that the Jacket Water System (JWS) is supplied with an after-cooler heater whose purpose is to maintain water temperature in after-cooler piping when the engine is not in operation. This proposed correction of EDG JSW A-CH function does not affect the ability of the EDG to start in a safe manner to mitigate consequence of an accident. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-089)

PR 960525108 Revision for DCP 2EA-1117 "Response to PR 960525108 revising UFSAR Figure 9.3-2B" - This evaluation involves the revision ofUFSAR figure 9.3-2B to correctly depict the plant. Two (2) valves were found installed in the field as isolations to Panels 827-2B and 2C. These valves type S-3 8 were not shown on the engineering drawings and apparently were installed as part of the original plant construction where all similar panels were to be isolated with S-38 valves. Because of the functional similarity of the S-3 8' s, the additional valves were deemed acceptable for end use. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-138)

TS2.0P-SO.ABV-0001(Q) "Modified Auxiliary Building Ventilation Operation" - This safety evaluation examines the effects and acceptability of the Unit 2 ABV system outage for the purpose of system refurbishment. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-142)

I

REFUELING INFORMATION DOCKET NO: 50-311 MONTH: OCTOBER 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5162 MONTH: OCTOBER 1996

1. Refueling information has changed from last month: YES ,___._ __,_. NO . X .

I

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 OCTOBER 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
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