ML18033B488

Forwards Request for Addl Info Re Util 900524 & 0713 Applications for Amend to License DPR-52

ML18033B488
Person / Time
Site:	Browns Ferry
Issue date:	08/17/1990
From:	Ross T Office of Nuclear Reactor Regulation
To:	Kingsley O TENNESSEE VALLEY AUTHORITY
References
TAC-76902, TAC-77144, NUDOCS 9008220138
Download: ML18033B488 (7)

Text

Docket No. 50-260 August 17, 1990 Hr. Oliver D. Kingsley, Jr.

Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 tlarket Street Chattanooga, Tennessee 37402-2801 I

References:

REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATIONS AHENDt'1ENT APPLICATIONS (TAC NOS.

76902 AND 77144)

(a) Letter from H. Medford (TVA) to NRC dated tlay 24, 1990 (b) Letter from H. Hedford (TVA) to NRC dated July 13, 1990 The Tennessee Valley Authority (TVA) submitted applications to amend the Technical Specifications (TS) of the Browns Ferry Nuclear Plant (BFN) in References (a) and (b).

After a preliminary review of these applications the NRC staff has determined that additional information from TVA will be neces-sary.

Enclosed are the staff's specific inquiries regarding References (a) and (b).

I would encourage you to provide us with this information as soon as possible so that we may continue to process TVA's TS amendment applications within the established restart schedule for Unit 2.

S incere ly, Original signed by Thierry Ross, Project tlanager Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/enclosure:

See next page OFC: P0 II-4/LA+

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ENCLOSURE REQUEST FOR ADDITIONAL INFORt'iATION OR CLARIFICATION BROllNS FERRY NUCLEAR PLANT - TECHNICAL SPECIFICATION NO. 287 REACTOR PRESSURE INSTRUh1ENT CHANNEL - UNIT 2

Reference:

Letter from N. Medford to NRC dated hay 24, 1990 (I)

Pressure switches 2-PS-68-93 8

94 are not identified in TS Table 3.2.A, "Primary Containment and Reactor Building Isolation Instrumentation".

They are.listed under Function as:

"Instrument Channel - Reactor High Pressure."

TVA proposes to identify pressure switches 2-PS-68-93 5 94 in TS Table 4.2.A, but this correction is not proposed for TS Table 3.2.A.

TVA should correct TS Table 3.2.A to identify pressure switches 2-PS-68-93 and 94.

(2)

The proposed functional test interval is once per three months, and the proposed calibration test interval is once per 18 months.

TVA's only justification for the proposing to increase the calibration frequency is as follows:

"The calibration frequencies for the new pressure switches are based on the manufacturer's recommendation and are supported by calculations."

The licensee offered no justification for the increased time between functional tests.

In general, TVA needs to provide a more detailed justification for their proposal to increase the TS surveillance requirements.

In particular, TVA should quantify or qualify any impact these changes may have on safety.

(3)

The staff requests TVA to provide schematic diagrams of valves 2-FCV-74-47, 2-FCV-74-48, 2-FCV-74-53, and 2-FCV-74-67.

(4)

The staff is unclear about the safety function of the Number I switch of pressure switches 2-PS-68-93 5 94.

In Enclosure 3 of TVA's TS amendment application, "Reasons and Justification for Changes" the following is stated:

"The only safety function performed by switches 2-PS-68-93 and 2-PS-68-94 is the high pressure isolation signal.....

This function is accomplished by SlM2."

On Page 2 the following is also stated:

"The only remaining safety function performed by switches 2-PS-68-93 and 2-PS-68-94 is the high pressure isolation signal..."

The licensee is asked to clarify these statements (i.e. "the only safety function" versus "the only remaining safety function").

REQUEST FOR ADDITIONAL INFORYiATION OR CLARIFICATION BROWNS FERRY NUCLEAR PLANT - TECHNICAL SPECIFICATION NO.

290 HPCI AND RCIC AREA TEMPERATURE CHANNEL - UNIT 2

Reference:

Letter from t4. Medford to NRC dated July 13, 1990.

(I)

The proposed action statement is:

"Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel(s) to OPERABLE status or place the inoperable channel(s) in the tripped condition."

The licensee also proposes to delete the following note in reference to the temperature monitors:

"Requires one channel from each physical location (there are 4

locations) in the steam line space."

TVA has not provided justification for changing the action statement and removing the above note.

TVA should provide the staff with an appropriate justification for these propo'sed changes and explain their impact on safety.

(2)

Each channel consists of four temperature monitors (pump room plus three torus areas).

The definition of an inoperable channel is not clear.

Is it the inoperability of any of the four temperature monitor s in a given channel?

Furthermore, the propose action statement does not place a time limit on how long an inoperable channel may be placed in the tripped position.

It is understood that the tripped position will place the logic in an appropriate condition to ensure isolation;

however, there is the additional concern that protracted operation with the logic in a partially tripped condition will make HPCI and RCIC more vulnerable to spur ious isolations.

The staff requests TVA to address the above question and concern.

(3)

TVA addressed spurious actuation as follows:

"The setpoints are established above the maximum expected room temperatures to avoid spurious actuation due to ambient conditions and below the analytical limits to ensure timely pipe break detection and isolation."

TVA's analysis does not take into account the loss of normal cooling in monitored areas, rate of temperature rise, or area temperature alarm setpoints to preclude spurious steam line supply line isolation.

The staff requests that TVA address these topics.

Mr. Oliver D. Kingsley, Jr.

- 2 CC:

Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 7A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. Edward G. Wallace

Manager, Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority 5N 157B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. John B. Waters, Director Tennessee Valley Authority ET 12A 9A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. W. F. Willis Chief Operating Officer ET 12B 16B 400 West Summit Hill Drive-Knoxville, Tennessee 37902 General Counsel Tennessee Valley Authority 400 West Summit Hill Drive ET 11B 33H Knoxville, Tennessee 37902 Mr. Dwight Nunn Vice President, Nuclear Engineering

.Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Dr. Har k 0. Hedford Vice President and Nuclear Technical Director Tennessee

'lalley Authority 6N 38A Lookout Place Chatta!!coga, Tennessee 37402-2801 Mr. 0. J. Zeringue, Site Director Browns. Ferry Nuclear Plant Tennessee Valley Authority P. 0.

Box 2000

Decatur, Alabama 35602 Mr. P. Carier, Site Licensing Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.

Box 2000

Decatur, Alabama 35602 Hr. L. W. Hyers, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.

Box 2000

Decatur, Alabama 35602

Chairman, Limestone County Commission P. 0.

Box 188

Athens, Alabama

'35611 Claude Earl Fox, M.D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Hr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant

'.S.

Nuclear Regulatory Commission Route 12, Box 637

Athens, Alabama 35611 Tenressee

'/alley l!uthority Rockville Office 11921 Rockville Pike Suite 402 Pockvil le, Maryland 20852

Distribution

~baoc Det ~ile NRC PDR Local PDR S. Varga G. Lainas F.

Hebdon S. Black B. Wilson P. Kellogg C. Patterson H. Krebs T. Ross D. t~oran F. Paulitz GGC E. Jordan ACRS (10)

GPA/CA BFN Reading File

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