ML20203B078

Requests Addl Info Re Conversion of Custom TS to Improved Std TS Format for Nuclear Measurement Analysis & Control Power Range Neutron Monitor Sys

ML20203B078
Person / Time
Site:	Browns Ferry
Issue date:	02/11/1998
From:	De Agazio A NRC (Affiliation Not Assigned)
To:	Zeringue O TENNESSEE VALLEY AUTHORITY
References
BFN-98-001, BFN-98-1, TAC-M96431, TAC-M96432, TAC-M96433, NUDOCS 9802240201
Download: ML20203B078 (6)

Text

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February 11, 1998 Mr. O. J. Z ringut -

Chi:;f Nucirrr Officer and Esecutive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

SUBJECT:

BROWNS FERRY PLANT UNITS 1,2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING CONVERSION OF CUSTOM 'l ECHNICAL SPECIFICATIONS TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (TAC NOS, M96431, M96432, AND M96433)

Dear Mr. Zeringue:

By letter dated April 11,1997, Tennessee Valley Authority (TVA) propaed revisions to technical specifications to convert the Browns Ferry Nuclear Plant Units 1,2, and 3 custom technical specifications to the improved Standard Technical Specification (ISTS), format for the Nuclear Measurement Analysis and Control Power Ranga Neutron Monitor System. The NRC staff has reviewed your application, and has determined that additional information is required to complete the review.

A description of the information required is provided in the enclosure. Your prompt response will assist us in completing a timely review.

Sincerely, l

/s/

Albert W. De Agazio, Senior Project Manager Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Cacket No. 50-259,50-260,50-296 Serial No. BFN-98-001

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION:

Docket File B. Clayton

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ACRS F. Hebdon J. Johnson, Region 11 s

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February 11, 1998 I4.*f J. zeringue Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessse 37402 2801

SUBJECT:

BROWNS FERRY PLANT UNITS I,2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING CONVERSION OF CUSTOM TECHNICAL SPECIFICATIONS TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (TAC NOS. M96431, M96432, AND M96433)

Dear Mr. Zeringue:

By letter dated April 11,1997, Tennessee Valley Authority (TVA) proposed revisions to technical specifications to convert the Browns Ferry Nuclear Plant Units 1,2, and 3 custom technical specifications to the improved Standard Technical Specification (ISTS) format for the Nuclear Measurement Analysis and Control Power Range Neutron Monitor System. The NRC staff has reviewed your application, and has determined that additionalinformation is required to complete the review.

A description of the information required is provided in the enclosure. Your prompt response will assist us,in completing a timely review.

Sincerely, a%a?

. Dz?

Albert W.

Agazio, Seni r P ject Manager Project Directorate 11-3 Division of Reactor Projects -l/II Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260,50-296 Serial No. BFN-98-001

Enclosure:

As stated cc w/ encl: See next page

Mr. O. J. Zeringue BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. J. A. Scalice, Senior Vice President Mr. Mark J. Burzynski, Managar Nuclear Operations Nuclear Licensing Tennessee Valley Authonty Tennessee Valley Authority 6A Lookout Place 4J Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Mr. Timothy E. Abney, Manager Engineering & Technical Services Liceneing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 37402-2801 Mr. C. M. Crane, Site Vice President Regional Administrator, Region ll Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commiss;on Tennessee Valley Authority 61 Forsyth Street, SW., Suite 23T85 P.O. Box 2000 Atlanta, GA 30303-3415 Decatur, AL 35609 Mr. Leonard D. Wert General Counsel Senior Resident inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 10H Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville,TN 37902 Athens, AL 35611 Mr. Raul R. Baron, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Health Tennessee Valley Authority 434 Monroe Street 4J Blue Ridge Montgomery, AL 35130-1701 1101 Market Street Chattanooga, TN 37402-LB01 Chairman Limestone County Commission Mr. Karl W. Singer, Plant Manager 310 West Washington Street Browns Ferry Nuclear Plant Athens, AL 35611 Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 4

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'e REQUEST FOR ADDITIONAL INFORMATION DROWNS FERRY NUCLEAR POWER PLANTS. UNITS 1. 2. AND 3 (TAC NOS. M96431. M96432. AND M96433)

The following comments and requests for additional information only pertain to the conversion of the Browns Ferry Power Station (BFN) Units 1,2, and 3 Custom Technical Specifications to the improved Standard Technical Specification (ISTS) format for the Nuclear Measurement Analysis and Control Power Range Neutron Monitor System (NUMAC-PRNMS). The comments are based on instances whem the licensee's proposed technical specification changes deviate from the ISTS for the NUMAC-PRNMS.

QUESTION 1: SURVEILLANCE REQUIREMENTS Provide corrections or justification for the following surveillance requirements,

a. SR3.3.1.1.1 -The proposed surveillance frequency for BFN SR 3.3.1.1.1 (CHANNEL CHECK) should be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instead of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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b. SR 3.3.1.1.7 - The proposed surveillance frequency for BFN SR 3.3.1.1.7 (Calibrate the local power range monitors) should be 1000 MWD /T uverage core exposure instead of the stated 1000 effective full power hours. Change the surveillance frequency units or describe the equivalence between exposure in units of effective full power hours and bumup in units of M W D/T.

c. To be consistent with the ISTS, change BFN trip function 2.a from " Neutron Flux High, Setdown," to " Neutron Flux - High (Setdown)."

d. To be consistent with the ISTS, change BFN trip function 2.b from " Flow Biased Simulated Thermal Power-High," to " Simulated Thermal Power - High." This trip function has changed, and should be renamed to correspond to the NUMAC-PRNM function name.

e. Th3 notes for proposed BFN SR 3.3.1.1.13 (Perform CHANNEL CAllBRATION) state,

1. Neutron detectors are excluded.

2. For Function 2.a. not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

The second note should reference Function 1 (intermediate Range Monitors)instead of Function 2.a (Average Power Range Monitors Neutron Flux - High (Setdown)).

Enclosure l

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ISTS SR 3.3.1.1.17 requires staggered response time testing. This SR is not in the proposed BFN TS amendments. Either add ISTS SR 3.3.1.1.17 to BFN TS, or provide a justification for removing response time testing from the TS.

g. If SR 3.3.1.1.17 is added to the BFN TS, add ISTS SR 3.3.1.1.17 to BFN Function 2.e (Average Power Range Monitors 2-Out-Of-4 Voter).

QUESTION 2: BASES DESCRIPTION OF APRM FUNCTION 2.E The Bases description of APRM Function 2.e was changed to be consistent with the approved Bases des.ription in NEDC-32410P A. The first paragraph of the revised Bases description

states, Three of the four APRM channels are required to be OPERABLE for each of the APRM Fur'ctions. This Function (Inop) provides assurance that a minimum number of APRMs are OPERABLE....

The description in NEDC-32410P-A states, Three of the four APRM channels are required to be OPERABLE for each of the APRM Functions. This Function (inop) provides assurance that the minimum number of APRMs are OPERABLE....

The use of the underiined definite article, the, should be used instead of the underlined indefinite article, a, because only the definite article estabiishes a specific relationship to the TS requirements.

QUESTION 3: ADDITION OF REFERENCE 12 TO THE TS BASES The proposed TS amendment adds Reference 12 (NEDC-32410P-A; to the Bases discussion of TS LCO 3.3.1.1 Actions A.1, A-2, B.1, and B.2. This reference is correct, except the reference number should be 11 for BFN Unit 1.

QUESTION 4: PAGE B 3.3-50, SECTION B 3.3.2.1 The scope of the BFN TS Bases discussion for SR 3.3.2.1.4 is not consistent with the scope of the ISTS discussion. The ISTS discussion states:

The RBM setpoints are automatically varied as a function of power. Three Allowable Values are specified in Table 3.3.2.1 -1, each within a specific power range. The power at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channe?. Below the minimum power setpoint, the RBM is automatically bypassed. These power Allowable Values must be verified periodically to be less than or equal to the specified values. If any power range channel can be paced in the conservative condition (i.e., enabling the proper RBM setpvint). If placed in this condition, the SR is met and the RBM channelis not considered inoperable. As notod, neutron detectors are excluded from the Surveillance because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Neutron detectors are adequately tested in SR 3.3.1.1.2 and SR 3.3.1.1-8. The 18 month Frequency is based on the actual trip setpoint methodology utilized for these channels.

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The prope.ed BFN TS Bases discussion states, l

A CHANNFL CALIBRATION is a complete check of the instrument loop and sensor. This test verifies the channel responds to the measured parameier within the necessary range and accuracy. CHANNEL CAllBRATION leaves the channel adjusted to accot. t for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

As noted, neutron detectors are excluded from the CHANNEL CALIBRATION because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signa!. Neutro.1 detectors are adequately tested in SR 3.3.1.1.2 and SR 3.3.1.1.7.

The Frequency is based upon the assumption of an 18 month calibration inter /alin the determination of the magnitude of equipment drift in the setpoint analysis.

Increase the scope of the Bases discussion to be consistent with the ISTS.

REFERENCES:

1.

• Browns Ferry Nuclear Plant (BFN)- Units 1,2, and 3 - Technical Specifications (TS) Change 353SI-Power Range Neutron Monitor (PRNM) Upgrade with implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS (ARTS) Improvements and Maximum Extendt4 Lued Line Limit (MELLL) Analyses - Supplement 1 - Improved Standard Technical Specifications (ISTS) Format," Tennessee Valley Authority, April 11,1997.

2. " Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM)

Retrofit Plus Option I!! Stability Trip Function," NEDC-32410P-A, October,1995.

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