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==SUBJECT:==
==SUBJECT:==
SAFETY EVALUATION REPORT FOR TVA'S RESPONSE TO NRC BULLETIN 88-02 (TAC R00327/R00328) - SEQUOYAH UNITS 1 AND 2                              ,
SAFETY EVALUATION REPORT FOR TVA'S RESPONSE TO NRC BULLETIN 88-02 (TAC R00327/R00328) - SEQUOYAH UNITS 1 AND 2                              ,
We have reviewed the Tennessee Valley Authority (TVA) response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks In Steam Generator Tubes", submitted by its letter dated March 1,1988 for Unit 2 TVA did not identify any dented tubes in the steam generators. We conclude that TVA has met the requirements of Bulletin 88 '2 for reporting at this time. However, TVA has not comitted            :
We have reviewed the Tennessee Valley Authority (TVA) response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks In Steam Generator Tubes", submitted by its {{letter dated|date=March 1, 1988|text=letter dated March 1,1988}} for Unit 2 TVA did not identify any dented tubes in the steam generators. We conclude that TVA has met the requirements of Bulletin 88 '2 for reporting at this time. However, TVA has not comitted            :
to inspect for denting of tubes at the uppennost tube support plate during future tube inspections after the next refueling outage. It is the intent of the Bulletin that such inspections continue for the remaining life of the plant and that if denting is found, the provisions of Paragraph C in the Bulletin should apply. In lieu of such a comitment. TVA stated that it is implementing Paragraph C.1 and C.2 of the Bulletin as if denting were actually found to be present. The staff finds this approach to be acceptable provided the details of TVA's program are submitted as specified in the Bulletin. Furthermore, actions taken to fulfill Paragraph C.2 of the Bulletin are subject to NRC review and approval, again according to a schedule consistent with Paragraph          '
to inspect for denting of tubes at the uppennost tube support plate during future tube inspections after the next refueling outage. It is the intent of the Bulletin that such inspections continue for the remaining life of the plant and that if denting is found, the provisions of Paragraph C in the Bulletin should apply. In lieu of such a comitment. TVA stated that it is implementing Paragraph C.1 and C.2 of the Bulletin as if denting were actually found to be present. The staff finds this approach to be acceptable provided the details of TVA's program are submitted as specified in the Bulletin. Furthermore, actions taken to fulfill Paragraph C.2 of the Bulletin are subject to NRC review and approval, again according to a schedule consistent with Paragraph          '
C.2 of the Bulletin. We request that you submit the details of the program before Unit 2 returns to power from the next refueling (Cycle 3) outage.
C.2 of the Bulletin. We request that you submit the details of the program before Unit 2 returns to power from the next refueling (Cycle 3) outage.
Unit I was addressed in TVA letter dated March 31, 1988, as supplemented by a          !
Unit I was addressed in TVA {{letter dated|date=March 31, 1988|text=letter dated March 31, 1988}}, as supplemented by a          !
letter dated July 6, 1988. TVA stated that Westinghouse has performed                  i a thennal/ hydraulic analysis of the Unit 1 steam generator using the                  I as-built antivibration bar ( AVB) locations. The methodology used to determine the depth of penetration of each AVB was provided by TVA in its letter dated March 31, 1988      In accordance with Section C.2 of the Bulletin        I where denting of tubes is present, the staff rust approve restert of Units              l where the restart is more than 90 days after the Bulletin was received.                  '
{{letter dated|date=July 6, 1988|text=letter dated July 6, 1988}}. TVA stated that Westinghouse has performed                  i a thennal/ hydraulic analysis of the Unit 1 steam generator using the                  I as-built antivibration bar ( AVB) locations. The methodology used to determine the depth of penetration of each AVB was provided by TVA in its {{letter dated|date=March 31, 1988|text=letter dated March 31, 1988}}       In accordance with Section C.2 of the Bulletin        I where denting of tubes is present, the staff rust approve restert of Units              l where the restart is more than 90 days after the Bulletin was received.                  '
Sequoyah Unit 1 is such a plant. For the staff to address restart of Unit 1            l in accordance with the Bulletin, we need to review the Westinghouse detailed            I thennal/ hydraulic analysis for Unit 1. We request that you provide this                I analysis within 30 days of receipt of this letter for the staff to support the restart of Unit 1. If the Westinghouee detailed analysis cannot be submitted before the scheduled Unit i restart, you need to explain the reason for the delay in submitting the analysis and orovide a tube-by-tube listing of stress ratios, stability ratios, fatigue usagt factors, and flow peaking factors for pF?
Sequoyah Unit 1 is such a plant. For the staff to address restart of Unit 1            l in accordance with the Bulletin, we need to review the Westinghouse detailed            I thennal/ hydraulic analysis for Unit 1. We request that you provide this                I analysis within 30 days of receipt of this letter for the staff to support the restart of Unit 1. If the Westinghouee detailed analysis cannot be submitted before the scheduled Unit i restart, you need to explain the reason for the delay in submitting the analysis and orovide a tube-by-tube listing of stress ratios, stability ratios, fatigue usagt factors, and flow peaking factors for pF?
SS08010161 8S0722                                                                  5 gR    ADOCK 05000327                                                            I
SS08010161 8S0722                                                                  5 gR    ADOCK 05000327                                                            I

Latest revision as of 04:56, 11 December 2021

Forwards Safety Evaluation Accepting Util 880301 Response to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes. Program for Implementing Paragraphs C.1 & C.2 of Bulletin Requested
ML20151H150
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/22/1988
From: Black S
NRC OFFICE OF SPECIAL PROJECTS
To: White S
TENNESSEE VALLEY AUTHORITY
Shared Package
ML20151H152 List:
References
IEB-88-002, IEB-88-2, TAC-R00327, TAC-R00328, TAC-R327, TAC-R328, NUDOCS 8808010161
Download: ML20151H150 (2)
v • d • e


Text

,

' o g UNeTED STATES

[ 3w g NUCLE AR REGULATORY COMMISSION

i t W ASHING TON, D. C. 20555
  1. July 22, 1988

% ,[,

Docket Nos. 50-327/328 Mr. S. A. White -

t Senior Vice President, Nuclear Power i Tennessee Valley Autnority 6N 38A Lookout Place 1101 Market Street ,

Chattanooga, Tennessee 37402-2801  ;

I

Dear Mr. White:

SUBJECT:

SAFETY EVALUATION REPORT FOR TVA'S RESPONSE TO NRC BULLETIN 88-02 (TAC R00327/R00328) - SEQUOYAH UNITS 1 AND 2 ,

We have reviewed the Tennessee Valley Authority (TVA) response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks In Steam Generator Tubes", submitted by its letter dated March 1,1988 for Unit 2 TVA did not identify any dented tubes in the steam generators. We conclude that TVA has met the requirements of Bulletin 88 '2 for reporting at this time. However, TVA has not comitted  :

to inspect for denting of tubes at the uppennost tube support plate during future tube inspections after the next refueling outage. It is the intent of the Bulletin that such inspections continue for the remaining life of the plant and that if denting is found, the provisions of Paragraph C in the Bulletin should apply. In lieu of such a comitment. TVA stated that it is implementing Paragraph C.1 and C.2 of the Bulletin as if denting were actually found to be present. The staff finds this approach to be acceptable provided the details of TVA's program are submitted as specified in the Bulletin. Furthermore, actions taken to fulfill Paragraph C.2 of the Bulletin are subject to NRC review and approval, again according to a schedule consistent with Paragraph '

C.2 of the Bulletin. We request that you submit the details of the program before Unit 2 returns to power from the next refueling (Cycle 3) outage.

Unit I was addressed in TVA letter dated March 31, 1988, as supplemented by a  !

letter dated July 6, 1988. TVA stated that Westinghouse has performed i a thennal/ hydraulic analysis of the Unit 1 steam generator using the I as-built antivibration bar ( AVB) locations. The methodology used to determine the depth of penetration of each AVB was provided by TVA in its letter dated March 31, 1988 In accordance with Section C.2 of the Bulletin I where denting of tubes is present, the staff rust approve restert of Units l where the restart is more than 90 days after the Bulletin was received. '

Sequoyah Unit 1 is such a plant. For the staff to address restart of Unit 1 l in accordance with the Bulletin, we need to review the Westinghouse detailed I thennal/ hydraulic analysis for Unit 1. We request that you provide this I analysis within 30 days of receipt of this letter for the staff to support the restart of Unit 1. If the Westinghouee detailed analysis cannot be submitted before the scheduled Unit i restart, you need to explain the reason for the delay in submitting the analysis and orovide a tube-by-tube listing of stress ratios, stability ratios, fatigue usagt factors, and flow peaking factors for pF?

SS08010161 8S0722 5 gR ADOCK 05000327 I

'7 PDC

\ )

i i

l .; '

2 the tubrs in the region of interest. The expression "region of interest" is interpreted by staff to include the region defined by the following bounderies:

(1) a tube row located at least two rows below the deepest AVB penetration depth, and (2) a tube row located at least one row above the shallowest AVB pene-tration depth. This request has been previously discussed with the Sequoyah site licensing u nager.

A copy of our Safety Evaluation Report for Unit 2 it, enclosed. A Safety Evaluation for Unit I will be the subject of a future letter.

The reporting and/or recordkeeping requirerrents contained in this letter .

affect fewer then ten respondents; therefore. OMB clearance is not required under P.L.96-511.

Sincerely.

Original signed by Suzanne Black. Assistant Director for Projects TVA Projects Division Office of Special Projects

Enclosure:

Safety Evaluation:

cc w/ enclosure See next page Distribution Docket File local POR NRC POP.

I Projects Rog.

J. Partlow J. Richardson S. Black B. D. Liaw l F. PcCoy i M. Sims J. Donohew J. Rutberg i F. Miraglia '

E. Jordan H.Garg)

ACRS(10 GPA/PA GPA/CA SQN Rdg. File _

OSP:TVA/LA h/PM TVA:$1EB

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TVA /f M

TVA:A0/P MSims - ew DSr h'l JFat 4tG SBlack 7/ /88 1/ y'88 7/ /88 7/ / 8 7/yn/88 7/t1/88

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