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Monthly Operating Rept for Jul 1997 for Salem Generating Station,Unit 2.W/970815 Ltr
	ML18102B525
Person / Time
Site:	Salem
Issue date:	07/31/1997
From:	Garchow D, Phillips R, Tisdel D; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LR-N970518, NUDOCS 9708250118
	Download: ML18102B525 (10)
	v • d • e

' .

, Public ::>ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG lJi 1997 LR-N970518 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for July, 1997, is attached.

I F. Gare ow General Manager -

Salem Operations RAR:tcp Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 JULY 1997 SALEM UNIT 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 the unit to operate in a safe, event free manner.

After the restart review, meet with the NRC and communicate the results of that review.

Refueling Information Docket No. 50-311

,Month:, July, 1997 Unit Name: Salem 2

Contact:

D. Tisdel Telephone: 609-339-1538 Month: July, 1997

1. Refueling information has changed from last month: Yes: No: X

2. Scheduled date for next refueling: Currently in outage.

Scheduled date for restart following refueling: To Be Determined

3. a. Will Technical Specification changes or other license amendments be required?

Yes: x No: Not Determined to Date:

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

Yes: X (for upcoming cycle) No: If no, when is it scheduled?

4. Scheduled date (s) for submitting proposed licensing action: N/A -

previously submitted

5. Important licensing considerations associated with refueling:

6. Number of Fuel Assemblies:

a. Incore: 193

b. In Spent Fuel Storage: 584

7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632

8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: October, 2016

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH July 1997 DOCKET NO.: ~5~0~-~31~1~--

UNIT NAME: Salem #2 DATE: 08-10-97 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 -

METHOD OF SHUTTING LICENSE -

DURATION DOIJN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION ..

NO. DATE TYPE' (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 4092 7-1-97 F 744 Fc 4 2422 Refueling Outage Extension

-ca 1 2 3 4 5 F: Forced Reason Method: Axhibit 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)

DOCKET NO.:

UNIT:

50-311 Salem 2 DATE: 08/15/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH JULY 1997 The following items completed during July 1997 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations 2EC-3341, Pkg. 1, Turbine Gland Sealing Steam and Leak Off System Modifications. This design change modifies the Turbine Gland Sealing Steam and Leak-Off system. The modifications include a new control valve, a new gland seal steam header pressure controller, a strainer with a drain valves and blowdown line, new internals for the high pressure turbine cylinder warming header steam pressure control valves, new turbine gland local steam pressure gauges and root valves, new orifice couplings, and the relocation of free blow valve piping connections.