ML18139C305

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Continued Operation W/ Unqualified Environ Equipment
ML18139C305
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/25/1983
From:
NRC
To:
Shared Package
ML18139C304 List:
References
NUDOCS 8304140006
Download: ML18139C305 (2)


Text

~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON,-D. C. 205.55

. '\\'.

SAFETY EVALUATION SUPPORTING CONTINUED OPERATION WITH "NOT ENVIRONMENTALLY QUALIFI~D".EQUIPMENT INTRODUCTION By letters dated*February 23-, March l.and* 9, 1983, Virgi.nia Electric and Power Company (the licensee) provided information related to justifying continued operation of the Surry Power Station, Unit Nos. land 2 with.equipment identified as not environm~ntalJy qualified. The equipment was identified as items II.B in the Safety Evaluation forwarded by NRC letter dated January 26, 1983.

The specifi.c items are. a wide range pressure transmitter in the reactor cool ant system (RCS) and a wide range level transmitter on the *steam generators.

Surry Unit l is currently shut down for refueling and the equipment in question will be replaced by qualified equipment prior to startup. Justification for continued operation of Surry Unit 2 follows.

JUSTIFICATION FOR CONTINUED OPERATION RCS Wide Range Pressure Transmitter The output from this device serves as an input to the subcooling meter. This device was installed in response to NUREG-0737 and provides information related to the margin of subcooling in the reactor coolant system. This device does not perform automatic actuations of safety equipment. Before this device was installed, operations personnel used pressure and temperature of* the reactor c.oolant system to ascertain the thermodynamic condition of the reactor coolant.

Currently installed instrumentation outside -the containment with remote indication*

in the control room and with a range of Oto 3000 psig can be used to infer the reactor coolant system margin: to saturation.

One pressure transmitter is located near the boron injection tank and the other is located on the charging/high head safety injection pump discharge header.

Withi.n the capacity/head curve* for this pump, these pressure indications less friction losses in the piping represent the reactor coolant system pressure. With the pumps at *runout flow, the coolant system i_ntegri ty has degraded to a point where margin to subcool ing cannot be maintained by the charging pumps.

Other safety systems including accumulators and low head safety injection pumps are operating to cool the reactor core.-:and*

repr.essurizing the reactor coolant system i_s not likely t~. occur.

This other instrumentation and the procedures used prior to installation of the device provide an alternate means of assessing reactor coolant system pressure and thus margin to subcooling.

The licensee has a.standing order in place to make operators aware of the alternative me.ans for determining reactor.,.

coolant system pressure.

In addition, a_Surry 2 refueling outage is planned for 8304140006 830325 PDR ADOCK 05000280 P

PDR

~..

I.

.-.,.._":'oo_:*: ****..

0 t,

I e..

May 1, 1983, which means that less than two months of operation in this manner will occ~r._ The probability of an event occurring prior to having a fully q'ualifie~ d~vice* is,very low.

Steam.Generator Wide Range Level The station emergency procedures require establi"shment of a water level in at least one (1) steam generator by indication in the narrow range or the wide range level transmitter span..

The wide range channel provides no safety function;_

it is used primarily for filling and dr&ining of the steam generators. A redun-

  • dant set of environmentally qualified instrumentation (narrow range level trans-mitters) exists to provide the required indication.

On the basis of the above, it is concluded that continued op*eration of the plant will have no effect on safety.

We have reviewed the 1 icensee' s justification for continued operation and.conclude

-that alternative equipment is available to perform the function required of the.

equipment identified as not qualified. This equipment-is being replaced now on Unit 1 and will be replaced o~ Unit 2 during the May 1983*refueling.

~.

,*,*... *. **.... --,.-~---- ---. -

... ~.. -* ---

.--~ --.,-*.***** -.. ********--*-:--""l.