ML19247A770

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Discusses Util Re Degraded Grid Voltage Generic Issues.Forwards Request for Addl Info Re Trip Setpoint Time Delay,Voltage Monitor Verification of IEEE Requirements & Channel Functional Tests
ML19247A770
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 07/03/1979
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Burstein S
WISCONSIN ELECTRIC POWER CO.
References
TAC-12955, TAC-12956, NUDOCS 7908020285
Download: ML19247A770 (3)


Text

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o UNITED STATES 8 "'^. ~, ",7, NUCLEAR REGULATORY COMML>SION i

W ASHINGTON, D. C. 20555 34 g

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July 3,1979 Docket Nos. 50-266 and 50-301 Mr. Sol Burstein Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, W1sconsin 53201 Dear Mr. Burstein; In conducting our raview of your July 28, 1977 letter relating to the degraded grid voltage generic issue as it applies to Point Beach Nuclear Plant Unit Nos. I and 2, we have determined that we will need-the additional information identified in the enclosure to continue the review.

In order for us to maintain our review schedule, your response is requested within 45 days of your receipt of this letter.

Please contact us if you have any questions concerning this request.

Sincerely

/

&c42/8 "

A. Schriencer, Chief Operating Reactors. Branch #1 Division of Operating Reactors

Enclosure:

Request for Additional Information cc: w/ enclosure See next page 446 185 m

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790802 6 M[

Mr. Sol Burstein Nisconsin Electric Power Company July 3, ~1979 cc:

Mr. Bruce Churchill, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D. C.

20036 Document Department University of Wisconsin Stevens Paint Library Stevens Point, Wisconsin 54481 Mr. Glen Reed, Manager Nuclear Power Division

.'cint Beach Nuclear Plant Wistwnsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 43201 9

RE0 VEST FOR ADDITIONAL INFORMATION POINT BEACH NUCLEAR PLANT NOS. 1 AND 2 DEGRADED GRID VOLTAGE 1.

Table 15.3.5-1 (Wiscensin Electric Power Company letter to NRC dated July 28,1977) has a trip set voltage of 3675 vo~its for degraded voltage condition.

State the time delay associated with this trip setpoint along with tolerances for the time delay and trip voltage in the Technical Specification change.

2.

Describe how the voltage monitors satisfy the requiremencs of IEEE 279-1971.

Include sufficient information to enable us to verify compliance with the requirements of the stand:rd.

3.

Table 15.4.1-1 (Wisconsin Electric Power Company letter to NRC dated July 28,1977) shows channel functional tests to be done every refueling cycl e. Give the basis for channel functional tests not to be done monthly as recommended by NRC letter, Table 4.3-2, Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements (Safety Evaluation and Statement o'f Staff Positions Relative to the Emergency Power Systems for Operating Reactors, dated June 2,1977).

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