ML19320B064

Forwards Addl Info Re Auxiliary Feedwater Sys Per 800514 Request

ML19320B064
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/01/1980
From:	Goodwin C PORTLAND GENERAL ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
NUDOCS 8007090227
Download: ML19320B064 (10)

Text

e July 1, 1980 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:

Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Sir:

Attached please find a copy of the additional information regarding the Trojan Nuclear Plant Auxiliary Feedwater (AFW) System that was requested in your letter of May 14, 1980. The attachment constitutes PGE's responses to the NRC positions identified in Enclosure 1 of your May 14, 1980 letter.

It should be noted that the information requested in Enclosure 2 of your October 3, 1979 letter (Item D - Basis for AFW System Flow Require-ments) had already been provided to the NRC (refer to C. Goodwin's letter to D. G. Eisenhut on November 5,1980) and this item is closed.

Sincerely, C. Goodwin, Jr.

Assistant Vice President Thermal Plant Operation and Maintenance

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Mr. Lynn Frank, Director' THIS DOCUMENT CONTAINS

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ATTACHMENT 1 PGE Response to the May 14, 1980 NRC Request for Additional Information on the Auxiliary Feedwater System A.

Short-Term Recommendations -(GS-2,

-4,

-5, -6 and -7)

NRC Positions PGE responses on these items are acceptable to the NRC except the Recommendation GS-7 which is still under the NRC review.

PCE Response No additional action is required.

B.

Additional Short-Term Recommendations 1.

NRC Position The Licensee's response to this recommendation is accept-able. However, the Licensee should verify that one of the condensate storage tank level indications and alarms will be powered from a battery-backed bus.

PGE Response The redundant CST level instrumentation and alarm switches, discussed in PGE Response of December 31, 1979, are all

- powered from an instrument bus which is energized from a ba ttery.

The CST level indication system with a low-low level alarm will be in service by the startup of Cycle 3.

2.

NRC Position The Licensee indicates that the AFW pump /dtiver vender strongly discourages performance of an endurance test.

It is our position that you perform an endurance test for each AFW pump prior to startup of Cycle 3 in accordance with the attached revised Additional Short-Term Recommendation 2.

. Note that the test requirement has been reduced from 72 hr.

to 48 hr.

The Licensee should commit to follow the provi-sions of the revised AFW pump endurance test requirements and submit the requested test information.

PGE Response hs ' endurance test has been ' conducted on both turbine-driven and diesel-driven AFW pumps prior to startup of Cycle 3 in accordance with the enclosure to the May 14, 1980 NRC let-ter, " Revised Short Ters Recommendation'2". Conditions and results of ' tha endurance test are presently being evaluated.

U A summary of the test results will be available for subm'ittal to' the NRC no later than July 25, 1980.

3.

NRC Position.

The Licensee's response to this recommendation is currently being evaluated by the Lessons Learned Implementation Task Force.

PGE Response

' No action is required.

4.

NRC Position.

The Licensee's response to this recommendation is acceptable.

PGE Response No action is required.

C.

Long-Term Recommendations 1.

NRC Position - Recommendation GL-2 The Licensee's response to this recommendation is acceptable (see Recommendation GL-4).

PGE Response No cdditional action is required (refer to Recommendation GL-4 for additional information).

2.

NRC Position - Recommendation GL-3 The Licensee's response to this recommendation is not com-plete. The Licensee 'should provide a description including the appropriate drawings of the modifications to be performed to ensure that the turbine-driven AFW pump, its associated systems and flow path will automatically provide adequate AFW flow for at least 2 hr. during a loss of all a-c power condition.

PGE Response As described in the PGE response of December 31, 1979, automatic initiation and-operation af one AFW pump, flow path and essential' instrumentation will be provided.

independent of any a-c power source for at least 2 hr.

-The turbine-driven-AFW pump and its associated systems are being modified in two parts to achieve an a-c power inde-pendence. First, the cooling water system to the turbine-driven.AFW pump,.previously supplied.from service water booster pumps, has been modified to accomplish a closed system of self-cooling. This modification provides cool-ing water circulation from the pump third-stage crossover through the lube oil bearing coolers and-back to the pump suction (see attached Figures 1 and 2). -1 C.

The second modification in the turbine-driven AFW system to be completed by the end of 1980 consists of a replu ement of steam inlet motor-operated valves to solenoid-operated pneumatic valves in order to achieve a-c independence. The solenoid valves are powered from the preferred a-c power source with a Seismic 1 backup' air supply system consisting of accumulator, check valves and associated piping (see attached Figure.3). The pneumatic valve will fail in the open position on loss of preferred a-c power and shall fail "as is" on loss of backup air supply.

3.

NRC Position

• Recommendation GL-4 The Licensee's response to this recommendation is accept-able; however, the Licensee should verify that the low suction pressure trips for tt, AFW pumps will be safety grade.

PCE Response The instrument and control systems for the low suction pressure trips of the AFW pumps are safety grade (Class 1E) and are designed to withstand the design seismic event.

Each AFW pump has its own channal.ized low suction pressure trip instrument loop.

4.

NRC Position - Recommendation GL-5 See Recommendation GS-7 above.

PGE Response No action required.

5.

NRC Position - Addition of Motor-Driven AFW Pump The Licensee' response to this recommendation is acceptable.

However,,the Licensee should provide us with copies of the revised AFW system drawings for the additional motor-driven pump.

PGE Response We are presently modifying the Trojan plant P&ID to reflect design change of-additional motor-driven AFW pump. The final revision of the P&ID has not been completed; therefore, for your information, we have attached a copy of the Interim Drawing Chan6e Notice (Figure 4) and a sketch describing the motor-driven pump (Figure 5).

6.

NRC Position - AFW System Pipe Break The Licensee's response to this recommendation is not accept-able.

It is our position that adequate protection be provided for the. diesel-driven AFW pump for postulated rupture of the turbine-driven AFW pump discharge piping in the diesel-driven -

e pump room.

In addition, the Licensee should ensure that the new motor-driven AFW pump train is separate from exist-ing AFW-pump trains in order to ensure that a break in the AFW system (not associated with the motor-driven pump train) could not affect the motor-driven pump.

In lieu of the above, the Licensee can describe the means for achieving a safe shutdown condition by use of other available systems following such a postulated event.

PGE Response We are continuing our evaluation on this subject. Our response will be provided to the NRC by July 25, 1980.

D.

NRC Position - Basis for AFW System Flow Requirements The Licensee indicaces that a response to Enclosure 2 of our Octoter 3, 1979 letter concerning a request for infor-mation on AFW system flow requirements will be provided.

The Licensee should provide this informatisn as soon as possible.

PGE Response The PGE response to Enclosure 2 of the NRC letter of October 3,1979 regarding AFW system flow requirements has been already submitted to the NRC (refer to C. Goodwin's letter. to D. G. - Eisenhut on February 5,.1980).

Thus, this item is closed.

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