ML20141D478

Responds to FOIA Request for LER 50-255/85-23.Document Available in PDR

ML20141D478
Person / Time
Site:	Palisades
Issue date:	03/11/1986
From:	Grimsley D NRC OFFICE OF ADMINISTRATION (ADM)
To:	Graber L NUS CORP.
References
FOIA-86-116 NUDOCS 8604080095
Download: ML20141D478 (2)

See also: IR 05000255/1985023

Text

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~g UNITED STATES

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MAR 11 1986

Mr. Lyle Graber

Licensing Engineer

Licensing Infomation Service

NUS Corporation IN RESPONSE REFER

2536 Contryside Boulevard TO F0lA-86-116

Cleamater, FL 33575-2094

Dear Mr. Graber:

This is in regard to your request, pursuant to the Freedom of Information Act,

to which the NRC assigned the above number.

This is a partial response to your request. We will notify

you upon completion of search for and review of any additional

records subject to your request.

The staff has completed the search for and review of records

subject to your request, and this is the final response to

your request.

The NRC has no records subject to your request.

~

Records subject to your request are available for public

inspection and copying at the NRC Public Document Room (PDR),

M 1717 H Street, NW, Washington, DC 20555, as noted on the

enclosure (s). The PDR accession number is identified beside

each record description.

X Records subject to your request are being made available for

public inspection and copying at the NRC Public Document Room

(PDR), 1717 H Street, NW, Washington, DC 20555, in the PDR

file folder under the above number and your name. These

records are listed on the enclosure.

We are enclosing a notice that provides information about

charges and procedures for obtaining records from the PDR.

Sincerely,

fE

Donnie H. Grimsley, Director

Division of Rules and Records

Office of Administration

Enclosure: As stated

8604080095 860311

PDR FOIA

CARDE86-116 PDR

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Re: F01A-86-116

APPENDIX

1. 11/18/85 Palisades Licensee Event Report No. 50-255/85-23

w/ enclosure. (3 pages)

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US Nuclear Regulatory Commission

Document Control Desk

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DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT -

LICENSEE EVENT REPORT 85-023 - POSSIBLE LOW TEMPERATURE

OVERPRESSURE PROTECTION SYSTDI SETPOIhT ERROR

Licensee Event Report (LER)85-023 (Possible Low Temperature Overpressure

Protection System Setpoint Error) is attached. This event is reportable to

the NRC per 10CFR50.73(a)(2)(i) and 10CFR50.73(a)(2)(ii).

Brian D Johnson (Signed)

Brian D Johnson

Staff Licensing Engineer '

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CC Administrator Region III. USNRC

NRC Resident Inspector - Palisades

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On October 17, 1985 with the Plant on shutdown cooling, it was determined that

the Low Temperature Overpressure Protection LTOP system may not adequately

protect the Plant. Power Operated Relief Nalve setpoints had not been

adjusted when the pressure / temperature operation curves were shifted to

account for revised reactor vessel limits due to neutron fluence. After an

engineerin's analysis, it was determined that administrative controls would be

put in place to protect the Plant from, low temperature overpressure during the

two limiting events and that no unreviewed safety question exists. These

administrative controls are in place and further investigation and evaluation

concerning new LTOP setpoints is underway.

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On October 17, 1985 at 1730 with the Plant on shutdown cooling, it was

determined that the Low Temperature Overpressure Protection (LTOP) system (AB]

may not adequately provide low temperature overpressure protection to the

reactor vessel when viewed from the most conservative standpoint with regard

to reactor vessel stresses. The Power Operated Relief Valve (PORV) [RV]

setpoints were not revised when the pressure / temperature operation curves were

shifted to account for revised reactor vessel limits which results from the

increase neutron fluence over plant life.

Engineering analysis determined that to protect the Plant from exceeding

allowable pressure / temperature limits during the two most limiting low

temperature overpressure events ie : inadvertent start of a High Pressure

Safety Injection (HPSI) pump or a Primary Coolant Pump (PCP) start with a

steam generator temperature 70*F higher than PCS temperature, the following

administrative controls would be required: First, the inadvertent start of a

HPSI pump would be protected against by pulling breaker fuses for both HPSI

pumps during cooldown and implementing restrictive administrative controls

concerning fuse reinstallation. Second, a PCP will be lef t running or all

pump breakers will be racked out and tagged. In the event these actions

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cannot be met restrictions will be imposed on primary to secondary side

temperature differentials or a vent path will be established in accordance

with Technical Specification requirements for inoperable PORVs. These

administrative controls are in place, no unreviewed safety question exists,

and new LTOP setpoints are being investigated and evaluated.

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