IR 05000272/1981026

IE Insp Repts 50-272/81-26 & 50-311/81-26 on 810929 & 1013-15.No Noncompliance Noted.Major Areas Inspected: Electrical Interaction Analysis for Auxiliary Feedwater Sys & RHR Sys & Verification of Fire Protection Program

ML18086B119
Person / Time
Site:	Salem
Issue date:	11/20/1981
From:	Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18086B116	List: IR 05000272/1981026
References
50-272-81-26, 50-311-81-26, NUDOCS 8112090153
Download: ML18086B119 (4)

Text

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-272/81-26 Region I R

t N 50-311/81-26 epor o. _____ _

50-272 Docket N _

_..;;_:;_.=....=..;=---

DP R -70 Li c ens e No. _ __,D=P....,R,_-.i...:.75.,,___

Priority -------

Category --..l.l.-----

Licensee:

Public Service Electric & Gas Company 80 Park Plaza - 15A Newark, New Jersey 07101 Facility Name:

Salem Generating Station, Unit l and 2 Inspection at:

Hancocks Bridge, New Jersey Inspection conducted:

September 29, 1981 and October 13-15, 1981 Inspectors:

Approved by:

Inspection Summary:

Inspector Systems Section and Technical date signed date signed date signed 1r#J -

date signed Combined Inspection on September 29, 1981 and October 13-15, 1981 Re art No /81-26; 50-311/81-26.

Areas Inspected: Routine, ~nnounced Inspection consisting of a review of the-Unit 1 & 2 Electrical Interaction Analysis for the Auxiliary Feedwater System and the Residual Heat Removal System; verification of Fire Protection Program and Safe Shutdown capability of these systems in Unit The inspection consisted of 27 irispection hours on site and 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> direct inspection ~ffort off-sit Results:

No items of noncompliance were identifie Region I Form 12 (Rev. April 77}

( 8112090153 811123\\

1 PDR ADOCK 05000272 I G

PDR;

.:.*

DETAILS Persons Contacted Public Service Electric & Gas Company

• J. Destefano, Site Qualjty Assurance Engineer R. Kyle, Senior Engineer Electrical (via telephone-Newark)

• S. LaBruna, Maintenance Engineer

• H. Midura, Station Manager M. Shedlock, Lead Electrical Engineer Catalytic Engineering, In J. Wanner, Site Quality Assurance Manager U. S. Nuclear Regulatory Commission

• L. Norrholm, Senior Resident Inspector

• denotes personnel present at exit meetin.

Interaction Analysis - Document Review The inspector selected the following safety-related shutdown systems for review from the licensee 1 s final submittal of September, 1981 entitled 11 Fire Protection, Safe Shutdown and Interaction Analysis 11 * Auxiliary Feedwater System The Auxiliary Feedwater System, consisting of two motor driven pumps and one turbine driven pump, supplies water to the steam generators for reactor decay heat removal if the normal feedwater system is not availabl The licensee analysis was based on the interaction of all trains of the auxiliary feedwater system in the same fire zon The inspector reviewed the System Operation Logic Diagram Drawing No. 250960 and the Cable Diagram Drawing No. 25095 In addition, the inspector reviewed the Interaction Resolutions for Cable No B1D2-BT, 2B1D2A-BT, 2A1D-A, 2A1D2A-AT, 2FW317-CT, 2FW318-CQ, 2FW324-CT, 2B13YF-B, 2B13YF2-BT, 2Al3YF-A, 2A13YF2-AT, 2A13YF2B-AT, 2FW325-CT, 2FW399-AT, 2FW400-BT, Panel 207 and the Hot Shutdown Pane No items of noncompliance were identifie *

3 Residual Heat Removal System The Residual Heat Removal System is designed to remove residual and sensible heat from the core and reduce the temperature of the Reactor Coolant System during the second phase of plant cooldow The system consists of two redundant flowpaths each of which contains a heat exchanger, pump and associated piping and valve The inspector reviewed the System Operation Logic Diagram Drawing No. 250958 and the associated Cable Diagram Drawing Nos. 250961 and 25096 In addition, the inspector reviewed the Interaction Resolutions for the following:

Equipment (Components)

1. 21 RHR Pump

1. 22 RHR Pump PT-405 (RCS Pressure)

PT-403 (RCS Pressure)

Valve #2RH1 Valve #2RH2 Valve #2RH26 Valve #22RH29 Valve #22RH18 Valve #22RH19 Valve #21RH18 Valve #21RH19 Valve #21RH4/21SJ44

-- #21 RHR Pump Room Cooler Cable No A7D-A

- 2A7D2-AT

- 287D-8

- 287D2-8T

- 2RC213-AQ

- 2MS321-AQ

- 2RC27-8Q

- 2MS320-8Q

- 283YAH-8

- 283YAH2-8T

- 283YAH2A-8T

- 2A3YAK-A

- 2A3YAK2-AT

- 2A3YAK2A-AT

- 2C3YAV2A-CT

- 283Y8T-8

- 283Y8T2-8T

- 283Y8T2A-8T

- 2ACS38-8T

- 2ACS38A-8T

- 2ACS39-8Q

- 283Y8H2A-8T

- 2ACS33-AQ

- 2A3Y8K2A-AT

- 2A3Y8D2A-AT

- 2Al3YH-A

- 2A13YH2-AT

- 2Al3YH2A-AT

- 2A13YG2-AT

- 2A7D28-AT

- 2Al3YH2C-AT No items of noncompliance were identifie.

Fire Protection Program - Work Observations The.inspector performed a visual inspection of the following systems, accompanied by a licensee representative from engineering and quality assurance, to ascertain whether the fire protection program as described in the Final Interaction Analysis Report has been implemented for the following system Areas inspected as follows: Auxiliary Feedwater System Aux. Bldg Control Area - elevation 64 1-0 11 ref. dwg. P2B Aux. Bldg elevation 64 1-0 11 ref. dwg. P2C Penetration Area e 1 evat ion 78 1 -0 11 ref. dwg. P2E Aux. Bldg elevation 84 1-or; 11 ref. dwg. P2F & P2G Aux. Bldg e 1 evat ion 100 1 -0 11 ref. dwg. P2H & P2I Residual Heat Removal System Aux. Bldg elevation 64 1-0 11 ref. dwg. P2C & P2D Penetration Area elevation 78 1-0 11 ref. dwg. P2E & P2M Aux. Bldg elevation 84 1-0 11 ref. dwg. P2F & P2G Aux. Bldg elevation 100 1-0 11 ref. dwg. P2H & P2I No items of noncompliance were identifie.

Exit Meeting The inspector met with licensee representatives (denoted in Details, Paragraph 1) at the conclusion of the inspection on October 15, 198 The inspector summarized the scope of the inspection and the results as noted herei In addition, the licensee was informed that this inspection does not constitute approval of its final report dated September 11, 1981 on Fire Protection Program, Safe Shutdown and Interaction Analysi Approval must come from the NRG licensing office following their review.