ML20197J293

Forwards Safety Evaluation & SALP Input Re Util Request to Defer Installation of Qualified Source Range Monitors Until First Refueling Outage Scheduled for mid-1986.Deferment Acceptable

ML20197J293
Person / Time
Site:	Columbia
Issue date:	02/12/1985
From:	Houston R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-0786, CON-WNP-786 TAC-55288, NUDOCS 8502150259
Download: ML20197J293 (6)

Text

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Dec LJ FEQ 12 gg MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM: R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration

SUBJECT:

WNP-2 SOURCE RANGE MONITOR QUALIFICATION Plant Name: WNP.2 Docket No.: M Licensing Status: OR TAC No.: 55288 Responsible Branch: LB #2 Project Manager: R. Auluck Review Branch: ICSB Review Status: Complete The purpose of this memorandum is to. transmit the enclosed Safety Evaluation, prepared by the Instrumentation & Control Systems Branch (ICSB). The evaluation addresses the licensee's request to defer installation of qualified' source range monitors (SRMs) until the first refueling outage, currently scheduled for mid 1986. License Condition 2.C.16 to the WNP-2 license (NPF-21) requires that qualified SRMs be installed by March 31, 1985. Based on information provided by the licensee in letter G02 85 014 dated January 11, 1985, the ICSB has concluded that deferral of installation of qualified SRMs to the first refueling outage is acceptable. The Equipment Qualification Branch (EQB) assisted ICSB during their review.

The ICSB's assessment of licensee performance (SALP input) is provided in Enclosure 2.

L L n e_- ,c.

R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration

Enclosures:

As stated cc: See attached list

Contact:

R. Kendall, ICSB X29451 ,

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SAFETY EVALUATION ,

.WNP-2; DEFERRAL OF INSTALLATION OF OUALIFIED SOURCE RANGE MONITOR 5 (TAC 55288)

. BACKGROUND AND DISCUSSION The licensee (Washington Public Power Supply System) has identified neutron flux as a Type A variable as defined in Regulatory Guide 1.97 (Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident). The instrumentation used to dis-play Type A variables is required to conform to Category I design and qualifica-tion criteria which includes environmental qualification in accordance with 10 CFR 50.49 (Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants). By letter G02-83-693 dated August 3, 1983, the licensee requested to defer installation of qualified source range monitors (SRMs) until the first refueling outage, scheduled for mid 1986. The basis for the request was that qualified replacements for the existing SRMs did not exist in industry, and that the delay would allow sufficient time to complete qualification of one of several designs being developed at the time.

The staff approved deferral of installation of qualified SRMs, but only until March 31, 1985 instead of the first refueling outage as requested by the licensee. The WNP-2 license (NPF-21) was conditioned (License Condition 2.C.16. Item 3b) to require installation of qualified SRMs by March 31, 1985 because this is the date given in 10 CFR 50.49 as a goal for final environmental qualification of electric equipment for operating reactors. It is noted that the remainder of the instrumentation upgrades required as a result of the RG 1.97 review do not have to be implemented until the first ,

refueling outage as set forth in Item 3a of License Condition 2.C.16.

By letter G02-85-014 dated January 11, 1985, the licensee again requested to defer installation of qualified SRMs (beyond the March 31, 1985 date) to the first refueling outage. The basis for this request continues to be the unavailability of a completely qualified SRM. The licensee has indicated that deferral until the first refueling outage will allow them to evaluate avdilable alternatives and install qualified SRMs.

The staff's review has concluded that deferral of installation of qualified SRMs to the first refueling outage is acceptable as discussed below.

EVALUATION March 31, 1985 is the date given in 10 CFR 50.49 for electrical equipment important to safety installed at operating reactors to be environmentally qualified for its environment. This date is not a deadline for implementation (installation or upgrade) of instrumentation required to bring WNP-2 into con-formance with the recommendations of RG 1.97. Modifications required as a result of RG 1.97 are to be implemented on a plant specific schedule agreed to by the staff and the licensee that takes into account plant workloads, and optimizes the use of utility and NRC resources (see Supplement 1 to NUREG-0737 Requirements for Emergency Response Capability - Generic Letter 82-33). Instrumentation designed to Category I requirements in accordance with RG 1.97 which is installed after March 31, 1985, must be environmentally qualified at the time of installation.

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The licensee is not requesting an exemption or deviation from either the requirements of RG 1.97 or the environmental qualification rule (10 CFR 50.49).

Therefore, a justification for continued operation (JCO) is not necessary.

The licensee intends to replace the existing SRMs with fully qualified SRMs prior to startup following the first refueling. The existing flux monitoring instrumentation consists of four redundant safety related channels, with the exception of environmental qualification, similar to those used in other oper-ating BWRs. The licensee has stated that in the unlikely event of an accident condition prior to replacement, there are additional systems in place that will provide the operators with sufficient data to assess reactor conditions (e.g.,

control rod position monitors, reactor vessel and pressure monitors, etc.).

CONCLUSION The staff recognizes that environmental qualification of SRMs is an industry development item. The staff has allowed delays for implementation of specific RG 1.97 instrumentation items if adequate justification for the delays and commitments to install the qualified instrumentation within a reasonable time are received from the licensee. Based on our review of information provided by the licensee, we find their request to defer installation of qualified SRMs until the first refueling outage (consistent with the implementation date for other RG 1.97 instrumentation) to be acceptable, and conclude that the existing instrumentation is acceptable for interim operation.

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EMCLOSURE 2 ICSB SALP INPUT .

PLANT: WNP-2

SUBJECT:

TAC #55288 -

EVALUATION PERF0PJtANCE BASIS CRITERIA CATER 4RY

1. Management N/A No basis for assessment.

Involvement .

The licensee demonstrated an adequate understanding of the issue, and

2. Approach to

• I provided technically sound justification supporting their position.

Resolution of Technical Issues

3. Responsiveness N/A tio basis for assessment.

4. Enforcement N/A No basis for assessment.

llistory -

5. Reportable Events N/A No basis for assessment.

E. Staffing N/A No basis for assessment. .

No basis for assessnent.

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