ML20040A714

Advises That Early Nov 1981 Draft Request for Info Re Data Requirements for Steam Line Break/Feedwater Line Audit Is Being Transmitted to Westinghouse for Response.Response to Encl Addl Request for Info Requested No Later than 820215

ML20040A714
Person / Time
Site:	North Anna
Issue date:	12/29/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 8201210451
Download: ML20040A714 (3)

Text

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NRC'PDK PKreutzer-3 L PDR Gray File Docket flo. 50-339 TERA NSIC w

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DEisenhut

!!r. R. II. Leasburg OELD

/p Vice President - Nuclear Operations AE0D nECEWED Virginia Electric and Power Company IE-3

/m Post Office Box 26666 ACRS-10 l C

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Ricinond, Virginia 23261 T. Novak M it wwmam B~Sheron v'g,,

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Dear ifr. Leasburg:

J. Guttman SU JECT: DATA REQUIRE!!ENTS FOR STEN 4 LINE BREAK /FEEDWATER i

AUDIT - NORTH ANNA PONER STATION, UilIT NO. 2 (NA-2)

In early November 1981, we sent you a draft copy of additional r quired e

i infomation for !!A-2 regarding the subject as noted above. Our purpose in sending you a draft copy was to allow you the necessary time to assess when the requested infomation could be collected for submittal to the NRC. In our discussions with you regarding this matter, you indicated that your res.ponse would be made available no later than February 15, 1982.

On December 11, 1981, the NRC staff had a meeting with Westinghouse i

where NRC data needs were discussed for plant audits. At this meeting Westinghouse indicated that they would provide the required information i

for ilA-2 to the Virginia Electric and Power Company upon receipt of a femal request for the subject infomation noted above.

Therefore, as provided in the Enclosure to this letter, we are fomally transmitting the draft infomation request which was provided to you in November 1981. The additional information requested in the Enclosure to this letter should be submitted to the NRC no later than February 15, 1982.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, O'tB clearance is not l

required under P.L.96-511.

Sincerely, mi e'gnut tfi

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n1 TuramcIl Ro

. Clark, Ch [

i fj0221043; fo j[29 P

ADOCK o Operating Reactors Branch #3 l

jj Division of Licensing n

Enclosure:

Request for additional mL

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Enclosure l

ADDITIONAL REOUIRED INFORMATION FOR THE NORTH ANNA UNIT 2 AUDIT l

1.0 REACTOR YESSEL a.

Internal Flow Areas i

1. Flow distributors

2. Support plates

3. Tie plates j

4. Flow area at grid spacers j

b.

Point Kinetic Reactivity Feedback Coefficients for:

l. Unrodded EOL core

2. Fully rodded EOL core

3. EOL core with most reactive rod stuck during scram

4. Hot shutdown EOL core with most reactive rod withdrawn j

5. Specific core section directly affected by the stuck /

withdrawn rod (if different from previous cases)

The Specific Reactivity Coefficients Requested are:

1. Moderator temperature coefficient

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2. Moderator density coefficient

3. Doppler coefficient

4. Total control rod worth with and without most reactive rod stuck in the withdrawn position

5. Baron worth coefficients 2.0 STEAM GENERATOR (SG)

SG Series 51 Technical Manual TM-1440-C234 Needed to Supply a.

Inforcation Such As:

1. Feedwater downcomer geometry

2. Steam dome geometry and tube bundle flow resistance

3. Recirculation ratios from separators at various operating conditions

4. Tale bundle support plate geometry b.

Auxilliary Feed Flow as a Function of Operating Pumps 3.0 REACTOR COOLANT PUMPS Westinghouse Instruction,,1)apudl 57IO-100-03 Needed to Supply a.

Information Such as:

1. Rated information

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2.10 head curves b.

2D Head Curves 6

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Paga 2 of 2 ADDITIONAL REQUIRED INFORMATION (CONT.)

4.0 PRESSURIZER a.

Pressurizer Technical Manual TM-1440-CZ35 This manual is needed to supply information such as:

1.

Heater Rod Geometry 2.

Heater Rod Surface Area 3.

Spray Flow as a Function of Pressure 4.

Geometry and Resistance of Surge Line Inlet Basket 5.0 ECC System a.

Accumulator Line Resist:.nce Due to 3 Valves Y'

b.

LPIS Flow Verses Number ~of Operating Pumps 6.0 E0L Fuel Rod Geometry, Fuel Thermal Conductivity and Heat Capacity for the Following Burnups:

1. 10000 KJD/MTU

2. 29000 KdD/MTU

3. 30000 KdD/MTU e

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