ML20151J147
| ML20151J147 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/11/1988 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Miltenberger S Public Service Enterprise Group |
| References | |
| NUDOCS 8808020191 | |
| Download: ML20151J147 (2) | |
See also: IR 05000354/1988003
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11 JUL 1988
Docket No, 50-354
Public Service Electric & Gas Company
ATTN: Mr. Steven E. Miltenberger
Vice President and
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Chief Nuclear Officer
Post Office Box 236
Hancocks Bridge, New Jersey 09038
Gentlemen:
Subject:
Inspection No. 50-354/88-03
This refers to your letter cateo February 29, 1983, in response to our
inspection of January 25-29, 1983.
Thank you for providing us with additional documer,tation supporting instrument
loop circuit analysis calculations on effects of LOCA environment on instrument
accuracy,
This information will be reviewed and evaluated in determining
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compliance and implementation of 10 CFR 50,49 requirements.
Your cooperation with us is appreciated.
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Sincerely,
hekt.ndStrrtO71
ct
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V<JeA)
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Jac(de P. Durr, Cl def
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Engineering Branch
Division of Reactor Safety
CC:
5. LaBruna, General Manager, Hope Creek Operations
Scott B. Ungerer, Manager, Joint Generation Projects Department,
Atlantic Electric Company
L. A. Reiter, General Manager - Licensing and Reliability
Rebecca A. Green, Bureau of Radiation Protection
Public Document Room (PDR)
local Public Document Room (LPOR)
Nuclear Safety information Center (N5!C)
NRC Resident Inspector
State of New Jersey
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OFFICIAL RECORD COPY
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Region I Docket Room (with concurrences)
Management Assistant, ORMA (w/o encl)
DRP Section Chief
Robert J. Bores, DRSS
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Gentlement
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HOPE CREEK EQUIPMENT QUALIFICATION PROGRAM
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INSTRUMFNT LOOP ACCURACY
HOPE CREEK GENERATING STATION
DOCKET NO. 50-354
Durino the recent NRC team insnection of the Hooe Creek Eculoment
Qualification Program (NRC Inspection No. 50-354/88-03, January
25-29, 1987), an unresolved item was identified regardino
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safety-related instrumentation loop accuracy under Desion Basis
Accident conditions.
In particular, the inspectors cuestioned
the extent to which the effect of a worst case accident scenario
on safety-related instrumentation loop accuracy has been
considered.
Time constraints precluded the inspectors from
evaluatino this item in detail durino the inspection.
PSE&G has '
requested, in conversations with NRC Recion I subsecuent to the
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inspection, the occortunity to provide additional information
related to this issue.
This information is provided herein.
PSEEG has always considered the reouirements of instrument
setnoint and loop accuracy under the most decraded environ ental
conditions.
This consideration has been included in all phases
of the desion, enoineerino, nrocurement and installation of
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instrumentation circuits in order to minimize the effect of
environmental stressors on instrunentation loop accuracy.
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As part of the oricinal nurchase order specifications under which
the equipment in question was obtained for Hone Creek, circuit
operability recuirements and the potential dearadation to
instrument accuracy due to environmental parameters has been
addressed.
The deoradation of circuit ooeration was a maior
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concern durino the desion process and the preparation of
equipment and comoonent seccifications which led to the
development of the purchase order specifications.
This
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concern has been similarly addressed in the subsequent
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installation practices and operation and maintenance requirements
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apolied to the instrumentation.
Setpoint calculations were
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performed and instrument calibration methodology was developed to
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address loop accuracy requirements under various environmental
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parameters encountered during both normal and abnormal plant
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operation.
The f ollowino list summarizes the major elements
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involved in our assessment and assurance of instrumentation loop
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accuracy f or safety-related instrumentation which may be exposed
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to a harch environment.
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Design and engineering requirements which address the
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potential effect of environmental stressors on
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instrument accuracy.
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2.
Purchase order specifications and procurement
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methodology reflective of Item 1 above.
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Ecuipment Qualification review of specified
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instrumentation and accuracy requirements versus tested
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parameters and its relation to installed conditions.
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4.
Analysis of insulation resistance (IR) and leakaae
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currents encountered durino cable qualification testino
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and its relation to installed conditions of equipment to
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ensure acceptable cable IR values.
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5.
Responses to NRC Information Notices and Bulletins
relatino to deqradation of instrument accuracy, loop
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accuracy and setpoint limits.
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6.
Elimination of terminal blocks in junction boxes
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associated with instrument circuits in LOCA environments
to avoid possible circuit degradation.
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Installation of qualified instrumentation and circuit
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conficurations utilizing nuclear Qrado Raychem WCSF
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splicos and moisture intrusion seals.
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8.
Implementation of installation criteria and cuidelines
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in Bechtel Document E-1408. Wire and Cable - Notes and
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Details, during construction.
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Operation and Maintenance procedures.
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Through implementStion of these efforts, all known contributors
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to the dearadation of instrument accuracy have been considsred
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and included in the performance characteristics of the
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instrumentation and instrument loop circuits.
To support this
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position, PSE&G has analyzed the loop accuracy of selected worst
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case instrument loops for safety-related instruments and
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FES 2 91983
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circuits.
Instruments performino exclusively trio and
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post-accident .monitorino functions to attain and maintain safe
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shutdown of the reactor were considered.
Instrument setooints,
setnoint selection and loon accuracy calculations were performed
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with actual deoraded parameters for various loop circuit elements
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involved.
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Tynical calculations were made for a Rosemount Transmitter and a
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Weed RTD on the basis of worst case design basis accident
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conditions of the circuits and loop elements.
Deoraded circuit
parameters were obtained from the vendor qualification reports
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contained in the Eo documentation binders.
Total loon allowance
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(TLA) was calculated as:
TLA = [AL2 + CL2 + DL2 + PEA 2 + PMA2
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Where:
AL = Loop Accuraev
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CL = Loon Calibration Error
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DL = Loon Drift
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PEA = Primary Element Accuracy
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PMA = Process Measurement Accuracy
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Enoineerino iudoement was empleved in obtainino values for PEA
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and PMA.
No terminal blocks were evaluated as part of this effort as none
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are used in the drywell or in dich Energy Line Break areas for
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safe shutdown instrument and instrument circuit terminations,
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unless included by the instrument suppliers and snecifically
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tested in conjunction with the basic instrument qualification
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procrams.
Circuit analysis and loop accuracy calculations
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utilized naximum cable lengths of 1400 feet, 500 feet of which
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was conservatively assumed to be installed in the harsh
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environment.
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For the Rosemount transmitter loop, the calculated inaccuracy at
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the trin unit was 0.00754% of span.
The specifie circuit
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analyzed by the calculation was not "typical" due to the
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inclusion of features intendad to represent a worst case
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condition.
For example, Hope Creek desion does not typically use
1400 foot transmitter cables with 500 feet beino exposed to LOCA
conditions.
Typically, transmitters of this type are located in
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rooms where the maximum temperature does not exceed 1482F.
The
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worst case cable IR value was selected after thermal and
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radiation acino.
The leakace currents across the terminal blocks
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within the transmitter were not considered in the calculation as
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their effect is envelooed by the EO testino and device
specifications.
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For the RTD loop, the inaccuracy was calculated as 0.01964 of
span.
The assumptions for cable lenqth were the same as those
assumed for the worst case Rosemount transmitter loop.
Additionally, the RTDs analyzed were the three-wire type with the
third wire utilized as a reference.
Should the resistance of the
third wire chance due to a dearaded environment, the other two
wires would experience a proportional chance, thereby negatino
the potential detrimental effect on the instrument accuracy.
Other potential worst case instrument loons were evaluated
(thermocouples, IRMs/PRMs).
Due to the high input impedance
values presented by the individual components in these locos,
additional calculations were not deemed to be necessary.
The
Rosemount transmitter and Weed RTD calculations are available
on-site for NRC review, if requested.
In conclusion, PSE&G feels that the above calculations and
evaluations have indicated that instrument and loop accuracies
under all conditions of plant operation, includinq DBA, are
within acceptable calibration limits, instrument accuracy and
transient overshoot.
These efforts have confirmed that the
measuren which have been taken by PSE&G to assure safety-related
instrument and instrumentation loop accuracy are valid.
If You have any further cuestions, please do not hesitate to
Contact us.
Sincerely,
C
Attachment
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RB 2 S G54
Document Con *.rol Dask
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Mr.
G.
W. Diven5 ark
USNRC Licensinc Droject Manager
Mr.
R.
W.
Borchardt
USNBC Senior Resident Inspector
Mr.
W. T. Russell, Administrator
USNRC ReQion I
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Mr.
D. M.
Scott, Chief
Bureau of Nuclear Encineerino
DeDartment of Environmental Protection
380 Scotch Road
Trenton, NJ
08629
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