ML18102A186

Monthly Operating Rept for May 1996 for Salem Unit 1. W/960615 Ltr

ML18102A186
Person / Time
Site:	Salem
Issue date:	05/31/1996
From:	Garchow D, Heller R, Phillips R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606200216
Download: ML18102A186 (10)

Text

PS~G*

• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit June 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document 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 May is being sent to you.

(b;~

• David F: Garchow General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 475 Allendale Road*

King of Prussia, PA 19046

~----

' 9606200216 960531 PDR ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94

AVERA. DAILY UNIT POWER LEVEL e Docket No.: 50-272 Unit Name: Salem #1 Date: 06/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month May 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

Completed by:

• OPERATING DATA REPORT Robert Phillips Docket No:

Date:

Telephone:

50-272 06/10/96 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period May 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 3647 165864

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) -2458 -11191 100193722

19. Unit Service Factor 0 0 60.5

20. Unit Availability Factor 0 0 60.5

21. Unit Capacity Factor (using MDC Net) 0 0 54.6

22. Unit Capacity Factor (using DER Net) 0 0 54.2

23. Unit Forced Outage Rate 100

• 100 23.4

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

The outage type changed to Forced outage on the first day of this reporting period.

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

To be determined.

8-1-7.R2

• Jan-April was/, but due to no service hours; the approved equation of : Forced outage hrs (Forced outage hrs + Unit Service hrs) now equals 100%e

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH May 1996 DOCKET NO.: ~5~0_-=27~2..____ _~

UNIT NAME: Salem #1 DATE: 06/10/96

• 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 4092 05-01-96 F 744 FC 4 ---------- HJ 2422 Nuclear Steam Generator Systems.

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: MAY 1996 UNIT NAME: S.A...LEM 1 DATE: 06/10/96 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-3425, Pkg. 1 "Security System - CCTV Camera Installation "B" Building Roof' Rev. 0 - The DCP adds three new cameras to the roof of "B" Building to provide surveillance coverage at the circulating water intake structure. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-108)

2. Temporary Modifications (TMOD)

TMOD 96-14 "Temporary Ventilation For Support OfDCP lEC-3505 Implementation" Rev. 0 - This temporary modification package provides an alternate source of ventilation to the Unit 1 Control Room, Electrical Equipment Room, Data Logging Room, and Relay Room areas which are normally supplied from the Unit 1 Control Area Air Conditioning System (CAACDS). In order to support implementation ofDCP lEC-3505, the Unit 1 CAACS will be out of service intermittently, and therefore, will be unavailable to provide ventilation to the areas listed above.

The temporary modification assures temperatures are maintained below the technical specification value, safety margin is not reduced. (SORC 96-055)

TMOD 95-073 "Isolation of 12A CC Heat Exchanger" Rev. 1 - The purpose of this TMOD is to isolate the service water to the 12A half of the 12 Component Cooling Heat Exchanger. This will allow return of 12 Component Cooling Heat Exchanger back to service with on-going repairs to Service Water valves associated with the 12A half of the heat exchanger. The temporary modification will not affect the operability of the

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MAY 1996 UNIT NAME: SALEM 1 DATE: 06/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-3 3 9-5162 component cooling system. Adequate margin exists in the design of the 12 Component Cooling Heat Exchanger that each half is capable of handling loads generated while the plant is defueled. Operability is not affected and therefore there is no reduction in the margin of safety as defined in the basis of any Technical Specification bases. (SORC 96-057)

3. UFSAR Change Notice (SCN)

SCN 96-038 "Accident Analysis Update" - This change implements new analyses and revises text in four Chapter 15 accidents in the Salem UFSAR. The accidents affected are: Excessive Heat Removal Due to Feedwater System Malfunctions; Major Reactor Coolant System Pipe Ruptures (Large Break Loss-Of-Coolant-Accident, only); Major Rupture of a Main Feedwater Line, and Mass and Energy Releases to Containment Following a Steamline Rupture. The results for the re-analyses of these accidents do not violate or change acceptance limits. Design failure points and system limitations remain unchanged. Hence, there has been no change to the margin of safety as defined in the basis of any technical specification. (SORC 96-057)

SCN 95-17 "Changes to the Salem Generating Station Organization Structure and Responsibilities" - The Nuclear Business Unit (NBU) has been re-organized to improve the direction, control, oversight, and accountability over nuclear plant operations and support functions. The NBU organization changes addressed by this proposal are any changes which hecame effective through April 18, 1996. The proposed changes reflect organization structure and responsibilities effective April 18, 1996, editorial enhancements, and clarifications. There is no reduction in the level of management control, responsibilities, training and qualifications, authority or commitments. The revised organization should improve alignment of responsibilities, and management focus on activities related to plant safety.

(SORC 96-057)

10CFR50.59 EVALUATIONS DOCKET NO:

• 50-272 MONTH: MAY 1996 UNIT NAME: SALEM 1 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 SCN 96-44 "Loss ofCCW Flow to RCPs: FSAR Section 9.2.2.8.2 Revision" - This 50.59 evaluates the SER Supplement 3 of the NUREG-0517 and clarifies FSAR Section 9.2.2.8.2 by revising the UFSAR such that it meets the intent of the SER. It also serves as an additional safety evaluation document for the previously performed procedure changes of S !/S2. OP-AB.RCP-001 (Q) Rev. 3 and Sl/S2.0P-AB.CC-000l(Q) Rev. 2. The revised UFSAR will not reduce the margin of safety, as described in the bases for any Technical Specifications. (SORC 96-057)

SCN 96-16 "Response to PR 960209175 Making Clarifications to UFSAR"

- PR #960209175 identified items that need to be corrected in the Salem Generating Station UFSAR. The pages affected are 10.4-2 through 10.4-4. The proposal does not reduce the margin of safety as defined in the basis of any Technical Specifications. Sections 3/4.3 "Instrumentation," 3/4. 7 "Plant Systems" and 3/4.11 "Radioactive effluent" of the Salem Units 1 and 2 Tech Specs and their bases were reviewed in order to arrive at this determination. (SORC 96-068)

4. Procedures and Revisions Security Plan "Salem-Hope Creek Security Plan" - The Salem-Hope Creek Security Plan is revised to implement Technical Specification Amendment No. 181/162 (Salem) and Amendment No. 95 (Hope Creek), which involved the deletion of two security-related items, which are required to be relocated to the Security Plan. The first item is the requirements for SORC review of the Security Plan and its implementing procedures. The second is the requirements to audit the Security Program every twelve months. The SORC review requirement is added to the introduction to the Security Plan. The audit requirement already exists in the Plan in paragraph 13 .1 and that the audit is under the cognizance of the Off-Site Safety Review staff.

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MAY 1996 UNIT NAME: SALEM I DATE: 06/10/96 COlVIPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd)

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-057)

5. Evaluations S96-0ll "Safety Evaluation for QA Organizational Changes" - This change to the UFSAR involves moving existing responsibilities between managers within the QA-NSR organization, specifically, the Quality Verification responsibilities previously assigned to the Manager - Quality Assessment are now assigned to the Manager - Corrective Action/Quality Services and the QA - Programs responsibilities previously assigned to the Manager - Corrective Action/Quality Services are now assigned to the Manager - Quality Assessment. This will allow the organization to more efficiently carry out theses functions. The proposed changes are administrative in nature and do not modify the margin of safety defined and maintained by Technical Specifications. (SORC 96-058)

S-C-CN-MEE-1073 "Condensate System Design Pressure Reconciliation" Rev. 0 -

The design basis engineering evaluation S-C-CN-MEE-1073 Rev. 0, provides the basis for taking exception to the system Code of record for the associated piping, vessels and valves.

This evaluation maintains the intent of the Code such that no safety concerns or adverse accidents may occur. Technical Specifications and their bases were reviewed in order to arrive at this determination. (SORC 96-058)

II .*

REfUELING INFORMATION DOCKET NO: 50-272 MONTH: MAY 1996 UNIT NAME: SALEM 1 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : MAY 1996 Refueling information has changed from last month: YES . X . NO ,,_._ ____,,

Scheduled date for next refueling: (to be determined)

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 989 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 MAY 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