ML18089A560

Forwards Listed Proprietary & Nonproprietary Info Re Inadequate Core Cooling Instrumentation,Tmi Action Item II.F.2,per 831117 SER Request.Proprietary Info Withheld (Ref 10CFR2.790)

ML18089A560
Person / Time
Site:	Salem
Issue date:	04/04/1984
From:	Liden E Public Service Enterprise Group
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML18089A561	List: ML18089A560 ML18089A562 ML18089A563
References
TASK-2.F.2, TASK-TM NUDOCS 8404160167
Download: ML18089A560 (6)

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e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department April 4, 1984 U. s. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D. C.

20555

y Attention

Mr. Steven A. 'yai;:'ga, Chief Operating Reactojs Branch,

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Dear Mr. Varga:

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INADEQUATE CORE COOLING INS~RUMENTATION TMI ITEM II.F.2 SALEM GENERATING STATION, UNITS NO. l AND 2

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DOCKET NOS. 50-272 AND 50-311 No.. 1 1,:

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~r NRC letter, dated November 17, 1983, transmitted the Safety Evaluation Report for the Inadequate Core Cooling Instru-mentation (ICCI) installed in Salem Units No. 1 and 2 and re-quested additional information in Enclosure 1 and 2 of the letter.

Following is a response to this request for addi-tional information: :

1.

Calibration procedure for the Reactor Vessel Level Monitoring System (RVLIS) -

enclosed are copies of the following documentation as you have requested.

i)

Reactor Vessel Level Instrumentation System Manual -

"Microprocessor Equipment -

3D/P Cell Design -

June, 1983".

(Proprietary) ii)

Reactor Vessel Level Instrumentation System Manual -

"Microprocessor Equipment -

3D/P Cell Design -

June,*

1983". (Non-proprietary)

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The Energy People ' {- ~~ ,,_,O~ ~tJO" fO'- ~,of, ' "'1~,c o*'-1 * .,..i *' 95-2168 (SOM) 11-82

Mr. Steven 4/4/84 iii) iv) Trip Report ICD-IS-(82)-080, used to check out, cal-ibrate and collect heat-up data for Microprocessor REVLIS for Salem Unit No. 1. Procedure NSD-EIS-82-11, "Pump Performance Curve Measurement," used to determine the wide-range delta P vs temperature curve. v) Procedure NSD-EIS-82-09. "Vessel Level Monitor System Scaling Calculations for Salem Unit No. l." These documents are regarded by Westinghouse as proprietary in accordance with applicable provisions of 10CFR 2.790. An af-fidavit submitted by Westinghouse requesting withholding of the above document from public disclosure is also enclosed. The calibration and test information for Unit No. 2 has not been received from Westinghouse. This information is expected to be available by April 30, 1984. We will transmit this information to you as soon as we receive it from Westinghouse.

2.

PSE&G letter, dated December 23, 1983, stated that the validation of the Emergency Operating Procedures incorporating RVLIS was scheduled for completion by January 9, 1984. However, due to some unanticipated delays in acceptance of the training simulator, the entire Emergency Operating Procedures Validation Program is running behind the original schedule. The expected completion date for this validation program is March, 1985. During this program, RVLIS will be incorporated into the emergency procedures and validated through table top exercises. Completion of the program will be docu-mented which will be available for future NRC inspection. RVLIS will be added to the training simulator 12 months after it is completely implemented at the plant (which includes completion of Emergency Operating Procedure Violation Program).

3.

The technical specification dealing with ICCI is being prepared using the guidance of Generic Letter 83-37. The schedule for submittal is being negotiated with the Project Manager as allowed by the generic letter. Any technical specification modification for Core Exit Thermo-couple (CET) system is pending the resolution of the qual-ification issue.

Mr. Steven 4/4/84

4.

Temperature measurement and compensation are not provided for all independently run vertical sections of impulse lines. There is no error in level since all the risers without compensation are within the same ambient environment. This applies to all the sensing lines of Units No. 1 and 2. This information was verbally transmitted to us by Westinghouse. We will confirm this upon receipt of written documentation from them.

5.

PSE&G has developed the following position concerning the qualification of the Core Exit Thermocouples for deter-mining the approach to Inadequate Core Cooling.

a.

Containment - The in-containment portion of the ICCI system utilizes the existing incore thermocouples for instrumentation monitoring. The existing sixty-four (64) installed incore thermocouples for Unit No. 1 (sixty-five (65) in Unit No. 2) are of Type K design. Upon exiting the Reactor Vessel head area, the CET design will incorporate qualified Combustion Engineering, Inc. (CE) Connectors and Mineral Insulated (MI) cables. This MI cable will be routed from the RV Head region to four CE supplied qualified connector plates located above the head area. Use of MI cables will assure adequate cable separation in the vicinity of the Reactor Vessel head (see Figure 1 attached). The thermocouple cables leaving the CE supplied connector plates, are environmentally qualified tables (in lieu of MI cables) and will be routed to redundant heated Reference Junction Box (RJB). In order to assure physical separation, the junction boxes are located at opposite ends of the containment and are separated by approximately thirty-five (35) feet. Qualified IEEE cable is finally routed from their respective junction box to separate electrical pene-trations, thereby, providing the maximum physical separation available. The MI cables and qualified connector assemblies are presently scheduled for installation during the Fifth Refueling Outage for Unit No. 1 and the Spring, 1985 Outage for Unit No.

2.

Mr. Steven 4/4/84 Except for the RJB, and cable connectors to the RJB, PSE&G proposed ICC In-Containment Design meets the intent of NUREG-0737 by providing qualified Type K thermocouples, limited Mineral Insulated Cable and qualified connectors to the Reactor Vessel Head and CE supplied connector plates. The RJB and associated connectors have not been environmentally qualified. However, these components are located on elevation 132', well above the maximum flood height (elevation 86'). PSE&G is presently investigating the feasibility of qualifying the RJB and associated con-nector design for in containment use.

6.

The primary display channel utilizes the station computer which is energized from an uninterruptible power supply. The backup display system is supplied from redundant station power sources. Although, these display systems are not Class lE, they are located in a mild environment, thereby, negating the requirement of performing a "harsh" environment qualification analysis. PSE&G is presently investigating the feasibility of utilizing a fully qualified backup display system in accordance with NUREG 0737, Section II.F.2.

7.

Refer to Item 6 above.

8.

A detailed description of the final integrated display system for ICC information will be provided upon resolution of the CET system design. - Item 6 Implementation Letter Report

1.

The RVLIS for both Units No. 1 and 2 have been installed. The functional testing and calibration for both units are being finalized. The Unit No. 1 test and calibration results are enclosed for your information and review.

2.

During the RVLIS functional testing and calibration, three deviations from the original RVLIS design were identified. These three deviations (denoted as Kits #1, 2, and 3) will be corrected as denoted below. The details associated with the three following design modifications will be maintained at the Salem site facilities.

a.

Kit #1: Installed on both units. Includes minor circuit modifications to enhance the compatibility and operability of the system.

Mr. Steven 4/4/84

b.

Kit #2: The Field Change Notice and hardware have been shipped to the site. This incorporates human factor and environmental/seismic qualification changes, 0 to 120% analog output scale change, steam density compensation algorithm, 3 position key switch to the microprocessor drawer, removal of containment monitor features from the existing system. The modification is tentatively set for April, 1984, for both units. The NVRAM boards for Unit No. 2 have been modified. Unit No. 1 NVRAM boards must still be released by Salem for modifications.

c.

Kit #3: Software and hardware is tentatively set for delivery in May, 1984, for both units. Kit #3 will include the following changes: The addition of a holddown clamp for the remote display power supply. New software program for the remote display. Addition of filter capacitors to the daughterboards.

3.

Refer to Item 2 (Enclosure 2) above. The appropriate documentation (i.e. DCR's) will be maintained at the plant site for NRC future inspection.

4.

Refer to the response to Item 3 of Enclosure 1.

5.

Request for NRC approval of the plant specific installation is pending the completion of calibration testing modifications.

6.

The Salem Emergency Operating Procedures were developed from the Westinghouse Owner's Group Guideline. Refer to the response to Item 2 of Enclosure 1. Attachments Sincerely, E. A. Liden Manager - Nuclear Licensing and Regulation

Mr. Steven C Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector 4/4/84}}