IR 05000354/1987010

Insp Rept 50-354/87-10 on 870316-20.No Violations Noted. Major Areas inspected:post-accident Monitoring Sys Conformance W/Rev 2 to Reg Guide 1.97.Open Item Identified Re Identification of Category 2 Equipment

ML20209C338
Person / Time
Site:	Hope Creek
Issue date:	04/07/1987
From:	Baer R, Vaughn Thomas, Villalva I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
Shared Package
ML20209C221	List: IR 05000354/1987010 ML20209C216
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 50-354-87-10, GL-82-33, NUDOCS 8704280651
Download: ML20209C338 (7)

Text

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.: 50-354/87-10 Docket No.: 50-354 License No.: NPF-57 Licensee: Public Service Electric & Gas Company 80 Park Plaza Newark, New Jersey 07101 Facility Name: Hope Creek Generating Station Inspection At: Hancocks Bridge, New Jersey Inspection Conducted: March 16-20, 1987

Inspectors:

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N 1. Villaiva Senior Resident Inspector, Lac BWR

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' V. D. Thomas Efatt Senior Instrumentation & Controls Engir.eer, IE

> Approved By: ( ? 'IbW h'h/7 7 R. L. Basr Date Chief, EGCB, DEPER, IE Inspection Sunnary: Inspection of March 16-20, 1987 r

(Inspection Report No. 50-354/87-10)

Areas Inspected: Special announced inspection of representative subsystems of the post-accident monitoring system at the Hope Creek

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Generating Station to assess conformance with Regulatory .

Guide 1.97, Revision Results: No violations were identified; however, one open item was identified.

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PDR ADOCK 05000354 O PDR 1

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DETAILS ,

1.0 Persons Contacted

Public Service Electric and Gas Company (PSE&G)

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• A. E. Giardino, Manager - Station QA P. M. Krishna, Assistant to the General Manager J. Cicconi, Planning Manager

• G. C. Connor, Operations Manager

• J. J. Hagan, Maintenance Manager B. Barkley, Systems Engineering E. Rush, Senior I&C Supervisor

• J. Lawrence, Licensing W. Merritt, Technical Department

• N. Champion, Quality Assurance M. Rogers Operations Department D. Gellerman, Systems Engineering J R. Beckwith, Station Licensing. Engineering S. Funseth, I&C Supervisor M. Mortarulo, Electrical Engineering M. Massaro, Nuclear Systems Engineering R. Bhatia, Electrical Engineering

, J. Lin, Systems Analysis Group

• R. T. Griffith, Sr. Principal Engineer, QA

• J. R. Lovell, Radiation Protection Chemical Manager U. S. Nuclear Regulatory Commission D. Allsopp, Resident Inspector

• R. Borchardt, Senior Resident Inspector

• Denotes those present at the exit meeting on March 20, 1987.

2.0 Regulatory Guide 1.97 (Revision 2) Program 2.1 References Regulatory Guide 1.97, Revision 2, " Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident Hope Creek Generating Station (HCGS) Final Safety Analysis Report (FSAR) Volume 1, Chapter, 7, Section 7.5.1.3.4 - Post-Accident Monitoring Instrumentation, Amendment 5, dated 4/84 and Table 7. (RG 1.97 Revision 2 Response)

Safety Evaluation Report (SER) " Hope Creek Generating Station -

Docket No. 50-354 - Conformance to Regulatory Guide 1.97 Revision 2" dated June 25, 1985.

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2.2 Background Generic Letter No. 82-33 issued Supplement 1 to NUREG-0737 on December 17, 1982. This document specifies those requirements regarding emergency response capability that had been approved by the NRC for implementation and discusses in part the application of RG 1.97, Revision 2 to the emergency response facilities, including the control room and technical support center (TSC) at HCG '

Public Service Electric and Gas Company, the licensee for the HCGS pro-vided its response to the generic letter on April 15, 1983. The licen-

,see's letter referred to Section 7.5 and Table 7.5.1 of the FSAR for a review of the instrumentation provided to meet RG 1.97, Revision This inspection report summarizes our findings regarding the installation of the post-accident monitoring system at the HCGS instrumentation in relation to the requirements in RG 1.97, Revision .3 Overall Regulatory Guide 1.97, Revision 2 Inspection The inspectors ~ held discussions with various members of the licensee's staff and contractor personnel to assess the implementation of the re-quirements delineated in RG 1.97, Revision 2 at the HCGS. Towards this end, the following instrumentations measurement loops were inspecte . Reactor Coolant System Pressure Measurement Loops A and B Readout Location / Qualification -Power Supply Loop Sensor Device " Panel" Classification Channel / Class A BBPT3684A PI3684A MCR/"C" Q/EQ A/1E

B BBPT3684B PR3684B MCR/"C"- Q/EQ B/1E Inspection Findings:

The calibrated pressure range for each of the above reactor coolant loops is 0 - 1500 psig. Pressure measurements from each loop are being readout on a dedicated indicator and continuous pen recorder. The readout devices are installed on vertical panel "C" located in the main control room (MCR). Sensing and

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readout equipment used in loops A and B meet all criteria for Category 1 equipment and the recommendations specified in Regulatory Guide 1.97, Revision 2. No violations were identi-fied by the inspectors during examination of these redundant measurement loop .

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2. Reactor Water Level Measurement Loops A and B

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Power Supply

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Loop / Readout Location / Qualification Range Sensor Device " Panel" Classification Channel / Class A/

0-400" BBLT3622A LR3622A MCR/"C" Q/EQ A/1E B/

0-400" BBLT3622B LR3622B MCR/"C" Q/EQ B/IE A/

-150-60" BBLT3682A LI3682A MCR/"C" Q/EQ A/1E B/

-150-60" BBLT3682B LR3682B MCR/"C" Q/EQ B/1E A/

0-60" BBLT3683A LI3683A MCR/"C" Q/EQ A/1E B/

0-60" BBLT3683B LR3683B MCR/"C" Q/EQ B/1E Inspection Findings:

Three different ranges of reactor water level measurements were inspected. The ranges of installed equipment (0 to 400 inches,

-150 to 60 inches, and 0 to 60 inches) are in agreement with those specified in Table 7.5.1 of the licensee's FSAR and as accepted in NRC's SER for the HCG (Note: Table 7.5.1 con-tains the RG 1.97 list of displayed parameters, category desig-nation, variable types, and types of display instrumentation which is the basis of the NRC's SER. Sensing and readout equipment used in all loops designated above were found to meet all criteria for Category 1 equipment and the recommendations specified in RG 1.97, Revision No violations were identified by the inspectors during examina-tion of the above reactor water level measurement loop . Drywell Pressure Measurement Loops A2, B2, and A3 Loop / Readout Location / Qualification Power Supply Range Sensor Device " Panel" Classification Channel / Class A2/

-5-250 psig GSPT4960A2 PI4960A2/ MCR/"E" Q/EQ A/1E PR4960A2 B2/

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psig GSPT4960B2 PI4960B2/ MCR/"E" Q/EQ D/1E l PR4960B2 A3/

-5-5 psig GSPT4960A3 PI4960A3/ MCR/"E" Q/EQ A/1E PR4960A3

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Inspection Findings:

Two wide range (-5 to 250 psig) and one narrow range (-5 to 5 psig) drywell pressure measurement loops were inspected. The ranges selected are in agreement with those stated RG 1.97, Revision 2 and Table 7.5.1 of the licensee's FSAR. Sensing and readout equipment used in the drywell pressure measurement loops above were found to meet all criteria for Category 1 equipment and recommendations specified in RG 1.97, Revision A fourth pressure measuring loop was selected by the inspectors which had a RG 1.97 Category 2 classification and a 12 psia to 3

psig range. However, review of the licensee's documentation revealed that this particular drywell pressure measurement requirement was upgraded to a Category 1 status and then as-signed to the -5 to 5 psig measurement loop A3 above. RG 1.97, Revision 2 allows this type of integration where a variable is listed for more than one purpos No violations were identified by the inspectors during examina-tion of the above drywell pressure measurement loop . Suppression Pool Water Level Measurement Loops A and C Loop / Readout Location / Qualification Power Supply Range Sensor Device " Panel" Classification Channel / Class A/

0-180" LT48051 LR48051 MCR/"B" Q/EQ A/1E C/

0-180" LT4801 LI4801 MCR/"C" Q/EQ C/IE

Inspection Findings:

i Two Suppression Pool water level measurement loops were in spected. Sensing and readout equipment used in the measurement loops were found to meet all criteria for Category 1 equipment

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and the recommendations specified in RG 1.97, Revision l No violations were identified by the inspectors during examina- '

tion of the Suppression Pool water level measurement loops l abov . Suppression Pool Temperature Measurement Loops A and B Loop / Readout Location / Qualification Power Supply Range Sensor Device " Panel" Classification Channel / Class A/

0-300 F TE3647Al TR3881A1 MCR/"C" Q/EQ A/IE B/

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0-300 F TE364781 TR3881B1 MCR/"C" Q/EQ B/1E

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Inspection Findings:

Two Suppression Pool temperature measurement loops were in-spected. Sensing and readout equipment used in the measurement loops were found to meet all criteria for Category 1 equipment and the recommendations specified in RG 1.97, Revision No violations were identified by the inspectors during examina-tion of the Suppression Pool water level measurement loops abov . Drywell Atmosphere Temperature Measurement Loops A and B Loop / Readout Location / Qualification Power Supply Range Sensor Device " Panel" Classification Channel / Class .

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0-500 F TE4967A2 TR4967A2 MCR/"E" Q/EQ A/1E B/

0-500 F TE4967B2 TR4967B2 MCR/"E" Q/EQ D/IE Inspection Findings:

Two drywell atmosphere temperature measurement loops were inspected. Sensing and readout equipment used in the measure-ment loops were found to meet all criteria for Category 2 equipment and the recommendations as specified in RG 1.97, Revision 2, with one exception. The licensee admitted to an oversight regarding the criterion which requires specific identification of all Category 2 equipment mounted on the main control room panels. This criterion was not addressed in implementing the criteria specified in RG 1.97. The licensee has committed to correcting this deficiency in the near future and the senior resident inspector stated that he will follow this as an open item for the HCGS. This finding was discussed with the licensee during the site exit interview on March 20, 198 . High Pressure Coolant Injection Flow Measurement Loop Readout Location / Qualification Power Supply Loop Sensor Device " Panel" Classification Channel / Class FTN008E41 FICR600 MPR/"B" 1E Inspection Findings:

The above flow measurement instrumentation met all criteria specified for Category 2 equipment and the recommendations specified in RG 1.97, Revision 2, except for the specific identification requirement as noted in the drywell temperature measurement loops discussed above. Accordingly this finding is part of the previously mentioned open ite .

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2. Overall Evaluation:

As stated earlier in subsections 2.3.6 and 2.3.7 an open item concerning the lack of specific identification of Category 2 equipment was brought to the attention of HCGS management at the exit meeting. Namely, RG 1.97, Revision 2, specifies that instruments designated as Types A, B, and C and Categories 1 and 2 should be specifically identified on the control panel so that the operator can easily discern that the instruments are part of the post-accident monitoring system. However, the aforemen-tioned instruments are not so identified; therefore, this oversight is considered as being an open item (50-354/87-10-1).

3.0 Exit Interview:

The inspectors met with licensee representatives as denoted in paragraph 1 of this report at the conclusion of the inspection and summarized the scope and findings of the inspectors activities. The licensee acknowl-edged the findings as reported herein and did not identify any information as being proprietar _ _