ML20237G475

Application for Amend to License NPF-57,revising License Condition 2.C.13 to Modify Completion Date for Spds.Mod Necessary to Accommodate Installation of Upgraded Spds. Description of Change Encl.Fee Paid

ML20237G475
Person / Time
Site:	Hope Creek
Issue date:	08/18/1987
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20237G477	List: ML20237G475 ML20237G483
References
NLR-N87134, NUDOCS 8708240098
Download: ML20237G475 (5)

Text

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s Public Service Electric and Gas Company Ct:v!n E. Mittenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339 4199 Vice President .

Nuclear OWratons August 18, 1987 NLR-N87134 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR~ AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. In accordance with the requirements of 10CFR50.91(b)(1), a copy of this request has been sent to the State of New Jersey as indicated below.

This amendment request revises License Condition 2.C.13 for the Safety Parameter Display System (SPDS) to modify the completion date. The modification is necessary to accommodate installation of an upgraded SPDS. Attachment I contains further discussion and justification for the proposed revision. Since this work is scheduled for the first refueling outage (February and March 1988) and this amendment is necessary for startup from this outage, we request review and approval of this submittal to support this schedule. This submittal includes one (1) signed original, including affidavit and thirty-seven (37) copies pursuant to 10CFR50.4(b)(2)(ii).

If you should have any questions, please do not hesitate to contact us.

Sincerely, b it bd 8708240098 870818 DR ADOCK05000g4 Attachments Qe,O CHtc.tc Sf I60 *O

Document Control Desk 2 8-18-87 C Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. W. Borchardt USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M . Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628

Ref: LCR 87-12 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

Steven E. Miltenberger, being duly sworn according to law deposes and-says:

I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated August 18, 1987 , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, is true to the best of my knowledge, information and belief.

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Subscribej and SwornJo befpre me this /f day of tu v e , 1987 ,

LARAINE Y. BEARD '

Notary Public of New Jersey Notary Polic of New Jersey y Cornmission Expires May 1,1991 My Commission expires on l

l

DESCRIPTION OF CHANGE Revise Operating License Condition 2.C.(13) to read as follows:

(13) Safety Parameter Display System (Section 18.2, SSER No. 5)

Prior to the earlier of 90 days after restart from the first refueling outage or July 12, 1988, PSE&G shall add the following I parameters to the SPDS and have them operational: )

a. Primary containment radiation I

b. Primary containment isolation status

c. Combustible gas concentration in primary containment

d. Source range neutron flux REASON FOR CHANGE During validation and verification of the current SPDS, it was determined that the current system could not meet all design requirements including update response times, adequate data validation and the required parameters per License condition i 2.C.(13). PSE&G is replacing the current system with one capable I of meeting these requirements as well as having additional l capacity for future needs.

The hardware for the new system will be installed in Hope Creek prior to shutdown for the first refueling. This hardware includes a new computer and two new multiplexer. Testing of the communication links between the new and existing multiplexer and the computer and testing of the software will be performed prior to the refueling outage. Connection of the wiring from the field sensors to the new multiplexer cannot be performed at power without possibly affecting safe operation of the plant. These connections will be performed during the outage and will include inputs for the additional parameters in License Condition 2.C.(13). After the new connections are made, circuit checks will be performed to ensure proper operation and that there are no adverse effects on existing plant equipment. Testing of the signals from the eight existing multiplexer will also be performed at this time. This delay of testing until the outage is necessary since testing the new computer at power would inhibit operation of the present SPDS system. Testing of some of the sensors at power could have an adverse effect on plant operation. A method of rapidly transferring operation between computers will be employed during testing to ensure that the existing SPDS can be used immediately if necessary.

Some aspects of the system must be tested while the plant is in operation (e.g., system loading, dynamic time responses). This testing will be conducted during startup, power ascension and while the plant is operating after the outage.

l During this testing period following the outage, the present SPDS i computer system will be operational and rapidly available. After I

all testing and debugging of the new computer has been completed, the new SPDS will be placed in operation.

l It is anticipated that the testing and debugging phase of the new l SPDS startup will take 90 days after startup from the outage.

l Based on the current outage schedule, the date for completing the testing and placing the computer in service is July 12, 1988.

SIGNIFICANT HAZARDS CONSIDERATION The proposed change has been reviewed and determined to not constitute a significant hazards consideration per the requirements of 10CFR50.92 for the following reasons:

The proposed change does not significantly increase the probability or consequences of an accident previously evaluated.

The SPDS system is not a control system and serves only in an advisory capacity to the Operations staff. Additionally, the existing system will be operational until the new system is fully checked out and operational. Therefore, the proposed change does not affect the probability or consequences of previously evaluated accidents.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. Although a new system is being installed, it is similar in design to the existing system.. As stated before, the SPDS does not control operation in the reactor in any way and serves only as a source of information. The system is designed to be isolated from any safety related system. The isolation system for the new SPDS system will use appropriately qualified optical iralation devices. The existing system will be functional during the schedular extension necessary to make the new system operational. Therefore, the proposed change does not create a new or different kind of accident.

The proposed change does not significantly reduce the margin of safety. The schedular extension will not reduce the margin of safety in that the existing SPDS will remain operational during installation of the new system. The new system represents an improvement in the margin of safety by providing increased capabilities over the old system and is necessary to install the additional parameters as required by License Condition 2.C.(13).

The extension does not represent a significant reduction in the margin of safety since the existing SPDS system was found to not constitute a safety concern as stated in Section 18.2 of Supplement 5 to NUREG-1048. The extension is necessary to upgrade to fully meet the guidance of Supplement 1, to NUREG-0737. Thus, the proposed change does not significantly reduce the margin of safety.

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