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* Temessee Vaney Authonty. Post oftce Box 2(XXL Soddy Da,sy Temessee 37379 July 19,1995 TVA-SON-TS-95-15 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
* Temessee Vaney Authonty. Post oftce Box 2(XXL Soddy Da,sy Temessee 37379 July 19,1995 TVA-SON-TS-95-15                                                               10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555                                                                           ;
In the Matter of
Gentlemen:
)
In the Matter of                                                       ) Docket Nos. 50-327 Tennessee Valley Authority                                             )             50-328 SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)
CHANGE 95-15, " ALTERNATE PLUGGING CRITERIA FOR STEAM GENERATOR (S/G)
CHANGE 95-15, " ALTERNATE PLUGGING CRITERIA FOR STEAM GENERATOR (S/G)
TUBING - UNITS 1 AND 2" In accordance with 10 CFR 50.90 we are enclosing a requested amendment to License DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The proposed change revises TS surveillance requirements and bases to incorporate alternate S/G tube plugging criteria at tube support plate (TSP) intersections. The approach taken is similar to guidance given in the draft Generic Letter (GL) 94-XX, " Voltage-Based Tubes Affected by Outside Diameter Stress Corrosion Cracking," for alternate plugging criteria. TVA's proposed changes are similar to the Farley Unit 1 TS                   1 amendment that was submitted by letter dated May 31,1995. The basis for the change is that alternate plugging criteria maintains the structuralintegrity of the tubing during normal operating, transient, and postulated accident conditions.
TUBING - UNITS 1 AND 2" In accordance with 10 CFR 50.90 we are enclosing a requested amendment to License DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The proposed change revises TS surveillance requirements and bases to incorporate alternate S/G tube plugging criteria at tube support plate (TSP) intersections. The approach taken is similar to guidance given in the draft Generic Letter (GL) 94-XX, " Voltage-Based Tubes Affected by Outside Diameter Stress Corrosion Cracking," for alternate plugging criteria. TVA's proposed changes are similar to the Farley Unit 1 TS 1
I The proposed TS change is identified in Enclosure 1. The justification of the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in Enclosure 3.
amendment that was submitted by {{letter dated|date=May 31, 1995|text=letter dated May 31,1995}}. The basis for the change is that alternate plugging criteria maintains the structuralintegrity of the tubing during normal operating, transient, and postulated accident conditions.
A TVA commitmentis provided in Enclosure 4. Exceptions to the NRC's draft GL are               :
The proposed TS change is identified in Enclosure 1. The justification of the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in Enclosure 3.
provided in Enclosure 5.
A TVA commitmentis provided in Enclosure 4. Exceptions to the NRC's draft GL are provided in Enclosure 5.
While S/G TSP tube degradation at SON is not expected to be significant, TVA is submitting this TS change in advance of the upcoming Unit 1 Cycle 7 refueling outage           ,
While S/G TSP tube degradation at SON is not expected to be significant, TVA is submitting this TS change in advance of the upcoming Unit 1 Cycle 7 refueling outage to prevent an exigent request for alternate plugging criteria implementation. If a sufficiently high number of TSPs outside diameter stress corrosion cracking indications are detected during SON's Unit 1 Cycle 7 refueling outage, use of the proposed alternate plugging criteria will be preferred. Therefore, NRC approval of this TS change is requested to support the Unit 1 outage that is currently scheduled for September 9,1995.
to prevent an exigent request for alternate plugging criteria implementation. If a               I sufficiently high number of TSPs outside diameter stress corrosion cracking indications are detected during SON's Unit 1 Cycle 7 refueling outage, use of the proposed alternate plugging criteria will be preferred. Therefore, NRC approval of this TS change is requested to support the Unit 1 outage that is currently scheduled for September 9,1995.
9508010145 950719
9508010145 950719                                                             1g
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                                                                                                        )
PDR ADDCK 05000327 1g i
PDR       ADDCK 05000327                                                         i P                               PDR                                           t l 1
P PDR t
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L       A U.S. Nuclear Regulatory Commission Page 2 July 19,1995 TVA is aware that NRC plans to issue the generic letter for S/G alternate plugging criteria in the near future. TVA will work with NRC project management to resolve TS   ;
L A
implementation issues relative to the final GL.                                         l l
U.S. Nuclear Regulatory Commission Page 2 July 19,1995 TVA is aware that NRC plans to issue the generic letter for S/G alternate plugging criteria in the near future. TVA will work with NRC project management to resolve TS implementation issues relative to the final GL.
Please note that the proposed TS change is based princioally on the methodology         l documented in WCAP-13990. This WCAP was docketed to NRC under TS 94-09 on June 28,1994. As WCAP-13990 contains information proprietary to Westinghouse, the application for withholding the affidavit (CAW-94-641) signed by Westinghouse, the proprietary information notice, and the copyright notice provided in Enclosure 7 of the June 28,1994, letter are in effect.
l Please note that the proposed TS change is based princioally on the methodology documented in WCAP-13990. This WCAP was docketed to NRC under TS 94-09 on June 28,1994. As WCAP-13990 contains information proprietary to Westinghouse, the application for withholding the affidavit (CAW-94-641) signed by Westinghouse, the proprietary information notice, and the copyright notice provided in Enclosure 7 of the {{letter dated|date=June 28, 1994|text=June 28,1994, letter}} are in effect.
TVA requests a 45-day implementation period for this TS change following issuance.
TVA requests a 45-day implementation period for this TS change following issuance.
Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.
Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.
Sincerely, fk.
Sincerely, fk.
R. H. Shell Mcnager SON Site Licensing wor       and subsep'bpd byfore me thi /         day of LA /tf>d       1995
R. H. Shell Mcnager SON Site Licensing wor and subsep'bpd byfore me thi /
          -1                   !      /D W Notar'y pub'lic                   /
day of LA /tf>d 1995
My Commission Expires         meammtm o:p;n oct 21. m3 l
-1
Enclosures -
/D W Notar'y pub'lic
cc: See page 3                                                                         I l
/
My Commission Expires meammtm o:p;n oct 21. m3 Enclosures -
cc: See page 3 l
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e a                                                                 i U.S. Nuclear Regulatory Commission                           ;
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Page 3 July 19,1995 (Enclosures):
i U.S. Nuclear Regulatory Commission Page 3 July 19,1995 (Enclosures):
Mr. D. E. LaBarge, Project Manager                         .
Mr. D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North i
Nuclear Regulatory Commission                             !
11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)
One White Flint, North i
Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident inspector Sequoyah Nuclear Plant 2600 lgou Ferry Road l
11555 Rockville Pike Rockville, Maryland 20852-2739                             ,
Soddy-Daisy, Tennessee 37379-3624 Regional Administrator t
Mr. Michael H. Mobley, Director (w/o Enclosures)
U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 l
Division of Radiological Health                           ,
I
3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident inspector Sequoyah Nuclear Plant                                     '
2600 lgou Ferry Road                                       ,
l Soddy-Daisy, Tennessee 37379-3624 t
Regional Administrator U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, NW, Suite 2900                       ;
Atlanta, Georgia 30323-2711                               ;
l I
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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2                                             l DOCKET NOS. 50-327 AND 50-328                                         .
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l
(TVA-SON-TS-95-15) i t
DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-15) i t
LIST OF AFFECTED PAGES                                               ;
LIST OF AFFECTED PAGES Unit 1 3/4 4-7 3/44-9 3/4 4-10 l
Unit 1 3/4 4-7 3/44-9                                                   ;
3/4 4-14 l
3/4 4-10                                                   l 3/4 4-14                                                   l l                                             B 3/4 4-3 l                                                                                                         '
l B 3/4 4-3 l
8 3/4 4-4 Unit 2                                                     ;
8 3/4 4-4 Unit 2 3/4 4-11 l
3/4 4-11 l
3/4 4-13 3/4 4-14 3/4 4-18 B 3/4 4-3 8 3/4 4-4 l
3/4 4-13 3/4 4-14 3/4 4-18 B 3/4 4-3 8 3/4 4-4                                                   l l
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                                                                  . . . . . - . .            ,  ,~}}

Latest revision as of 01:31, 14 December 2024

Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-15, Alternate Plugging for SG Tubing
ML20086S231
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/19/1995
From: Shell R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086S232 List:
References
NUDOCS 9508010145
Download: ML20086S231 (4)
v • d • e


Text

.6

  • Temessee Vaney Authonty. Post oftce Box 2(XXL Soddy Da,sy Temessee 37379 July 19,1995 TVA-SON-TS-95-15 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley Authority

)

50-328 SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)

CHANGE 95-15, " ALTERNATE PLUGGING CRITERIA FOR STEAM GENERATOR (S/G)

TUBING - UNITS 1 AND 2" In accordance with 10 CFR 50.90 we are enclosing a requested amendment to License DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The proposed change revises TS surveillance requirements and bases to incorporate alternate S/G tube plugging criteria at tube support plate (TSP) intersections. The approach taken is similar to guidance given in the draft Generic Letter (GL) 94-XX, " Voltage-Based Tubes Affected by Outside Diameter Stress Corrosion Cracking," for alternate plugging criteria. TVA's proposed changes are similar to the Farley Unit 1 TS 1

amendment that was submitted by letter dated May 31,1995. The basis for the change is that alternate plugging criteria maintains the structuralintegrity of the tubing during normal operating, transient, and postulated accident conditions.

The proposed TS change is identified in Enclosure 1. The justification of the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in Enclosure 3.

A TVA commitmentis provided in Enclosure 4. Exceptions to the NRC's draft GL are provided in Enclosure 5.

While S/G TSP tube degradation at SON is not expected to be significant, TVA is submitting this TS change in advance of the upcoming Unit 1 Cycle 7 refueling outage to prevent an exigent request for alternate plugging criteria implementation. If a sufficiently high number of TSPs outside diameter stress corrosion cracking indications are detected during SON's Unit 1 Cycle 7 refueling outage, use of the proposed alternate plugging criteria will be preferred. Therefore, NRC approval of this TS change is requested to support the Unit 1 outage that is currently scheduled for September 9,1995.

9508010145 950719

)

PDR ADDCK 05000327 1g i

P PDR t

1

L A

U.S. Nuclear Regulatory Commission Page 2 July 19,1995 TVA is aware that NRC plans to issue the generic letter for S/G alternate plugging criteria in the near future. TVA will work with NRC project management to resolve TS implementation issues relative to the final GL.

l Please note that the proposed TS change is based princioally on the methodology documented in WCAP-13990. This WCAP was docketed to NRC under TS 94-09 on June 28,1994. As WCAP-13990 contains information proprietary to Westinghouse, the application for withholding the affidavit (CAW-94-641) signed by Westinghouse, the proprietary information notice, and the copyright notice provided in Enclosure 7 of the June 28,1994, letter are in effect.

TVA requests a 45-day implementation period for this TS change following issuance.

Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.

Sincerely, fk.

R. H. Shell Mcnager SON Site Licensing wor and subsep'bpd byfore me thi /

day of LA /tf>d 1995

-1

/D W Notar'y pub'lic

/

My Commission Expires meammtm o:p;n oct 21. m3 Enclosures -

cc: See page 3 l

i i

e a

i U.S. Nuclear Regulatory Commission Page 3 July 19,1995 (Enclosures):

Mr. D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North i

11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)

Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident inspector Sequoyah Nuclear Plant 2600 lgou Ferry Road l

Soddy-Daisy, Tennessee 37379-3624 Regional Administrator t

U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 l

I

{

1

+

b

)

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l

DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-15) i t

LIST OF AFFECTED PAGES Unit 1 3/4 4-7 3/44-9 3/4 4-10 l

3/4 4-14 l

l B 3/4 4-3 l

8 3/4 4-4 Unit 2 3/4 4-11 l

3/4 4-13 3/4 4-14 3/4 4-18 B 3/4 4-3 8 3/4 4-4 l

l i

,~

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