ML20197J546

Forwards Reactor Sys Branch SER Re Util 850227 Application to Amend License NPF-21,changing Tech Specs.Licensee Proposed Mods for HPCS Pump Discharge Pressure High Flow Signal Acceptable.Salp Input Also Encl

ML20197J546
Person / Time
Site:	Columbia
Issue date:	04/22/1985
From:	Houston R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-0797, CON-WNP-797 TAC-56945, NUDOCS 8505010379
Download: ML20197J546 (4)

Text

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J.PR 22 mna 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:

TECHNICAL SPECIFICATION CHANGES (WNP-2)

Plant Name: WPPSS Nuclear Project No. 2 Docket Number: 50-397 TAC No.: 56945 Responsible Branch: Licensing Branch #2 Project Manager: J. Bradfute Review Branch Reactor Systems Branch, DSI Enclosed is the Reactor Systems Branch SER with regard to the WNP-2 Tech'nical Specification Changes. The licensee's proposed modifications for HPCS pump discharge pressure-high flow signal are acceptable.

Enclosure 2 is our SALP input.

-...a. --

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

Enclosure:

As stated cc: R. Bernero A. Schwencer DISTRIBUTION J. Bradfute RSB S/Ls RSB R/F RSB Section B Members RSB P/F: WNP-2 GThomas R/F AD/RS Rdg.

BSheron CONTACT: G. Thomas, RSB WHodges x29445 GThomas Thomas /03,gd DS DS S DI B D'SIM/AD G :gd MWHodges B n RHodston

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ENCLOSURE 1 l

SAFETY EVALUATION REPORT WPPSS - NUCLEAR PLANT NO. 2 By letter dated February 27, 1985.(G02-85-098), Washington Public Power Supply System (the licensee) requested an amendment to the Technical Specifications of Facility Operating License No. NPF-21 for Nuclear Plant No. 2. Aoditional information and clarifications were provided by the licensee during a tele-conference on March 26, 1985.

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The Technical Specifications as presently written (Tables 3.3.2-1, 3.3.3-2 and 4.3.3.1-1) contain the requirements to perform a monthly Channel Functional Test and an annual (during refueling outage) Channel Calibration on the Pump j Discharge Pressure-High (pump running) instrumentation. The present HPCS design incorporates mininum flow valve logic based on concurrent conditions of high pump discharge pressure and low system flow. The pressure switch which i provides the high discharge pressure (pump running) input takes its signal i

l downstream of the pump discharga check valve. Consequently, upon securing the pump following closure of the test flow path, high pressyre can be trapped downstream of the check valve and result in the minimum flow valve remaining open with the pump off. This necessitates depressu?izing the system to close the valve.

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2-This amendment seeks to replace the high discharge pressure signal with a pump running input taken from the pump breaker. Thus, the valve would open on low flow and breaker closed (pump running) and would close on high flow or with the breaker open. With this design enhancement, the pump discharge pressure-high signal would no longer be used or needed.

The amendment eliminates drift and calibration errors associated with instru-mentation and their attendant failure modes. Actuation of the system itself is being made even more affirmative from the standpoint of signal reliability; that is, the proposed pump logic is a positive indication of the pump breaker position and will automatically reflect the status of the HPCS pump without any of the problems associated with instrument channels. Furthermore, the pump minimum flow logic will be functionally verified during the HPCS Pump Quarterly Operability Test as well as during the 18 month Logic System Functional Test.

We understand from the licensee that the original LPCS minimum flow valve logic is the same as now proposed for HPCS. According to the licensee only the pump discharge pressure switch is deleted. The pump discharge pressure indications are not changed or deleted. The deletion of the pump discharge pressure switch will not result in any decreased safety, hence the proposed amendment to Technical Specification Tables 3. 3. 3-1, 3. 3. 3-2 and 4. 3. 3.1-1 i s acceptable to the staff.

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ENCLOSURE 2 j l

' WPPSS - Nuclear Plant No. 2 -- Systematic Assessment of Licensee Performance l

I Function Areas:

1. Management involvement in assuring quality.

Technical review of the submittal indicates that the management reviews are timely and technically appropriate.

Rating: Category 2*

2. Approach to resolution of technical ' issues from a safety standpoint.

The licensee showed a general understanding of the technical issue and used acceptable approaches.

Rating: Category 2

3. Responsiveress to NRC Initiatives.

N/A . . _ ,,

4. Staffing (including management).

N/A ,

5. Reporting and analyses of reportable events.

N/A

6. Training and effectiveness and qualification.

N/A

7. Overall rating for functional area: 2 d

Reference:

NRC Appendix 0516 - Systematic Assessment of Licensee Performance.

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