ML18101B004

Monthly Operating Rept for Aug 1995 for Salem Unit 1.W/ 950911 Ltr

ML18101B004
Person / Time
Site:	Salem
Issue date:	08/31/1995
From:	Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9509190252
Download: ML18101B004 (9)

Text

,. e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit September 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 August are being sent to you.

Sincerely~

~.

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-l-7.R4 The power i9jn vou~~~902s2-95o831 ___ _

95*2168 REV. 6/9 PDR ADOCK 05000272 L

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.AVE~ DAILY UNIT POWER LEVEL e Docket No.: 50-272 Unit Name: Salem #1 Date: 09/11/95 Completed by: Robert Phillips Telephone: 339-2735 Month August 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 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

e OPERATING DATA REPORT e Docket No: 50-272 Date: 09/11/95 Completed by: Robert Phillips Telephone: 339-2735 Operating status

1. Unit Name Salem No. 1 Notes

2. Reporting 1Period August 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 744 5831 159288

12. No. of Hrs. Rx. was Critical 0 2660.9 104380.5

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) -5500 2532635 100214799

19. Unit Service Factor 0 45.1 63.0

20. Unit Availability Factor 0 45.1 63.0

21. Unit Capacity Factor (using MDC Net) 0 39.3 56.9

22. Unit Capacity Factor (using DER Net) 0 39.0 56.4

23. Unit Forced Outage Rate 100 54.9 22.8

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

To be dtermined.

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

To be determined.

8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1995 DOCKET NO;: "'"'5""'0'-..,.-=27...,2:..,,.,.---

UNIT NAME: Salem #1 *.

DATE: 9-10-95 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON *.REACTOR REPORT # CODE4 CODE 5 TO PREVENT RECURRENCE 2671 8-1-95 F 744 D 4 ----------- SH CKTBRK TECH. SPEC. 3.0.3 I

1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manua l 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 (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

lOC:fR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: AUGUST 1995 UNIT NAME: SALEM 1 DATE: 09/10/95 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 ov~r to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.

2. Temporary Modifications (T-Mod)95-028 "Boiler Feed Iron Sampling Modification" Rev. 0 - An iron entrainment sample system, consisting of an isolation valve, a pressure regulator, a flow meter, a heat exchanger, a filter assembly, and interconnecting tubing and fittings, will be connected to the Unit 1 Boiler Feedwater Drain Valve 12BF39.

This system will be used to obtain data on iron entrained in the feedwater en route to the 16B Feedwater Heater. This modification is in accordance with PSE&G pipe specs and will meet the pressure and temperature limitations of the system. A second isolation valve will be installed to improve modification isolation. This modification is installed on a secondary plant system with no safety related equipment. The equipment important to safety near this modification is weather tight and will function as per design and would not be impacted from a total failure of the temporary modification. There is no reduction in the margin of safety as defined in the bases for any Technical Specifications. (SORC 95-097)

3. Procedures SECG/HECG E-Plan "Salem ECG Sections I - 11, Hope Creek ECG Sections I-11, Emergency Plan Section 5" - The Salem and Hope Creek Event Classification Guides are being revised to provide an improved set of Emergency Action Levels (EALs) and Reporting Action

10C:fR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: AUGUST 1995 UNIT NAME: SALEM 1 DATE: 09/10/95 CO:MPLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd)

Levels (RALs) which are consistent with the revised NUMARC methodology on emergency classification. In addition to revising all EALs, a new document titled "Event Classification Guide Technical Basis", (ECGTB), is being provided for each ECG which will provide the ECG users with a basis and discussion for each EAL. The ECGTB will also provide the calculations and assumptions used to provide the EAL threshold values. Implementation of the NUMARC EALs does not reduce the effectiveness of the Emergency Plan based on NRC acceptance of the methodology. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-090) *

4. Safety Evaluations SCN95-037 "Revision of Organization Titles and Duties for Chief Nuclear Officer, Director Quality Assurance and Nuclear Safety Review, Chemistry and Radiation Protection Managers IAW Provisions ofT.S. Amendment 168/150" - This UFSAR revision changes the position titles for the Chief Nuclear Officer and President -

Nuclear Business Unit and for the Director - Quality Assurance and Nuclear Safety Review. There are no changes to the functional responsibilities for either position. The proposed reorganization splits the Radiation Protection and Chemistry organization into distinct departments (as reflected in Technical Specification Amendments 168/150). This change is anticipated to improve the oversight in both areas. These changes do not conflict with any Technical Specification requirement or reduce the margin of safety required by the Technical Specifications.

The specific programs and policies are still required by UFSAR Section 12.3.5, Procedures. (SORC 95-092)

SCN 95-39 "Increase in Tech Spec Minimum Volume Required in Diesel Fuel Oil Storage Tanks (Salem Amendments 170/152)" - The proposed revisions clarify implementation of the design basis for the storage capacity of the diesel fuel oil storage system. This clarification is necessary to resolve a potential deviation

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: AUGUST 1995 UNIT NAME: SALEM 1 DATE: 09/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 identified by the NRC during an EDSFI performed at Salem during August and September of 1993. The EDSFI identified that the SAR currently states each 30,000 gallon diesel fuel oil storage tank can supply one EDG with enough fuel oil to operate it for seven days at full load; however, the ability of the as-built system to meet this requirement could not be verified.

The proposed revisions are being made to provide an accurate description of the diesel fuel oil storage system design and operation in the SAR and to raise the Technical Specification fuel oil limit to an acceptable level. These changes, and the identified procedure changes, are being made to enable the diesels to operate for seven days at full load. The EDG fuel Oil Storage System meets the design basis goal by supplying approximately 4 1/2 days from the Diesel Fuel Oil Storage Tanks for 2 EDG operation or 2 112 days if 3 EDGs are in operation. The EPIP provides an action plan for alternate fuel oil supply to replenish the Diesel Fuel Oil Storage Tanks from on-site storage or offsite sources to ensure the required fuel supply for seven days. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-094)

REFpELING INFORMATION DOCKET NO:

• 50-272 MONTH: AUGUST 1995 UNIT NAME: SALEM 1 DATE: 09/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH : AUGUST 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 J _

b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NOJ_

If no, when is it scheduled? (to be determined )

Scheduled date(s) for submitting proposed licensing action: _ _ ___r.N~/~A=----,.----'--

Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore 0

b. In Spent Fuel Storage 973 ~-

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 AUGUST 1995 SALEM UNIT NO. 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