Text

Amendment Nos. 170 and 76 Regarding the Revision of Technical Specifications 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by Adopting Various Technical Specifications Task Force Travelers
	ML24285A207
Person / Time
Site:	Watts Bar
Issue date:	12/17/2024
From:	Kimberly Green; Plant Licensing Branch II
To:	Erb D; Tennessee Valley Authority
	Green K
References
	EPID L-2023-LLA-0172
	Download: ML24285A207 (1)
	v • d • e

December 17, 2024 Delson C. Erb Vice President, OPS Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 170 AND 76 REGARDING THE REVISION OF TECHNICAL SPECIFICATIONS BY ADOPTING VARIOUS TECHNICAL SPECIFICATIONS TASK FORCE TRAVELERS (EPID L-2023-LLA-0172)

Dear Delson Erb:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 170 to Facility Operating License No. NPF-90 and Amendment No. 76 to Facility Operating License No. NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2 (WBN), respectively. These amendments are in response to your application dated December 13, 2023.

The amendments revise WBN technical specifications 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by adopting various Technical Specifications Task Force travelers.

A copy of the related safety evaluation is also enclosed. Notice of issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391

Enclosures:

1. Amendment No. 170 to NPF-90

2. Amendment No. 76 to NPF-96

3. Safety Evaluation cc: Listserv

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License No. NPF-90

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated December 13, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 170 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: December 17, 2024 DAVID WRONA Digitally signed by DAVID WRONA Date: 2024.12.17 15:33:10 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 170 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Facility Operating License No. NPF-90 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 2.0-1 2.0-1 2.0-2 3.0-3 3.0-3 3.1-1 3.1-1 3.1-2 3.1-2 3.1-3 3.1-3 3.1-4 3.1-4 3.1-6 3.1-6 3.1-7 3.1-7 3.1-10 3.1-10 3.1-16 3.1-16 3.1-20 3.1-20 3.1-21 3.1-22 3.1-23 3.1-21 3.1-24 3.1-22 3.2-1 3.2-1 3.2-2 3.2-2 3.2-3 3.2-3 3.2-9 3.2-9 3.2-10 3.2-10 3.2-11 3.2-11 3.2-12 3.2-12 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3-4 3.3-7 3.3-7 3.3-8 3.3-8 3.3-9 3.3-9 3.3-10 3.3-10 3.3-15 3.3-15 Remove Pages Insert Pages 3.3-16 3.3-16 3.3-20 3.3-20 3.3-21 3.3-21 3.3-22 3.3-22 3.3-29 3.3-29 3.4-1 3.4-1 3.4-2 3.4-2 5.0-29 5.0-29

Amendment No. 170 Facility License No. NPF-90 (4)

TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration, or other activity associated with radioactive apparatus or components; and (5)

TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.

(1)

Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 170 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)

Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.

(4)

Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)

During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.

6/V

DWWV%DU8QLW

$PHQGPHQW

6$)(7</,0,766/V

6/V

5HDFWRU&RUH6/V

,Q02'(6DQGWKHFRPELQDWLRQRI7+(50$/32:(55HDFWRU&RRODQW

6\VWHP5&6KLJKHVWORRSDYHUDJHWHPSHUDWXUHDQGSUHVVXUL]HUSUHVVXUHVKDOO

QRWH[FHHGWKHOLPLWVVSHFLILHGLQWKH&2/5DQGWKHIROORZLQJ6/VVKDOOQRWEH

H[FHHGHG

7KHGHSDUWXUHIURPQXFOHDWHERLOLQJUDWLR'1%5VKDOOEHPDLQWDLQHG

IRUWKH:5%0'1%FRUUHODWLRQ

7KHSHDNIXHOFHQWHUOLQHWHPSHUDWXUHVKDOOEHPDLQWDLQHG)

GHFUHDVLQJE\)SHU0:'078RIEXUQXS

5&63UHVVXUH6/

,Q02'(6DQGWKH5&6SUHVVXUHVKDOOEHPDLQWDLQHGdSVLJ

6/9LRODWLRQV

,I6/LVYLRODWHGUHVWRUHFRPSOLDQFHDQGEHLQ02'(ZLWKLQKRXU

,I6/LVYLRODWHG

,Q02'(RUUHVWRUHFRPSOLDQFHDQGEHLQ02'(ZLWKLQKRXU

,Q02'(RUUHVWRUHFRPSOLDQFHZLWKLQPLQXWHV

/&2$SSOLFDELOLW\

DWWV%DU8QLW

$PHQGPHQW

/&2$33/,&$%,/,7<

/&2

KHQDVXSSRUWV\VWHP V5HTXLUHG$FWLRQGLUHFWVDVXSSRUWHGV\VWHPWREH

FRQWLQXHG

GHFODUHGLQRSHUDEOHRUGLUHFWVHQWU\LQWR&RQGLWLRQVDQG5HTXLUHG$FWLRQVIRUD

VXSSRUWHGV\VWHPWKHDSSOLFDEOH&RQGLWLRQVDQG5HTXLUHG$FWLRQVVKDOOEH

HQWHUHGLQDFFRUGDQFHZLWK/&2

/&2

7HVW([FHSWLRQ/&2DOORZVVSHFLILHG7HFKQLFDO6SHFLILFDWLRQ76

UHTXLUHPHQWVWREHFKDQJHGWRSHUPLWSHUIRUPDQFHRIVSHFLDOWHVWVDQG

RSHUDWLRQV8QOHVVRWKHUZLVHVSHFLILHGDOORWKHU76UHTXLUHPHQWVUHPDLQ

XQFKDQJHG&RPSOLDQFHZLWK7HVW([FHSWLRQ/&2VLVRSWLRQDO:KHQD7HVW

([FHSWLRQ/&2LVGHVLUHGWREHPHWEXWLVQRWPHWWKH$&7,216RIWKH7HVW

([FHSWLRQ/&2VKDOOEHPHW:KHQD7HVW([FHSWLRQ/&2LVQRWGHVLUHGWREH

PHWHQWU\LQWRD02'(RURWKHUVSHFLILHGFRQGLWLRQLQWKH$SSOLFDELOLW\VKDOOEH

PDGHLQDFFRUGDQFHZLWKWKHRWKHUDSSOLFDEOH6SHFLILFDWLRQV

/&2

KHQRQHRUPRUHUHTXLUHGVQXEEHUVDUHXQDEOHWRSHUIRUPWKHLUDVVRFLDWHG

VXSSRUWIXQFWLRQVDQ\DIIHFWHGVXSSRUWHG/&2VDUHQRWUHTXLUHGWREH

GHFODUHGQRWPHWVROHO\IRUWKLVUHDVRQLIULVNLVDVVHVVHGDQGPDQDJHGDQG

D WKHVQXEEHUVQRWDEOHWRSHUIRUPWKHLUDVVRFLDWHGVXSSRUWIXQFWLRQVDUH DVVRFLDWHGZLWKRQO\RQHWUDLQRUVXEV\VWHPRIDPXOWLSOHWUDLQRUVXEV\VWHP VXSSRUWHGV\VWHPRUDUHDVVRFLDWHGZLWKDVLQJOHWUDLQRUVXEV\VWHP VXSSRUWHGV\VWHPDQGDUHDEOHWRSHUIRUPWKHLUDVVRFLDWHGVXSSRUWIXQFWLRQ ZLWKLQKRXUVRU E WKHVQXEEHUVQRWDEOHWRSHUIRUPWKHLUDVVRFLDWHGVXSSRUWIXQFWLRQVDUH DVVRFLDWHGZLWKPRUHWKDQRQHWUDLQRUVXEV\VWHPRIDPXOWLSOHWUDLQRU VXEV\VWHPVXSSRUWHGV\VWHPDQGDUHDEOHWRSHUIRUPWKHLUDVVRFLDWHGVXSSRUW IXQFWLRQZLWKLQKRXUV

$WWKHHQGRIWKHVSHFLILHGSHULRGWKHUHTXLUHGVQXEEHUVPXVWEHDEOHWRSHUIRUP

WKHLUDVVRFLDWHGVXSSRUWIXQFWLRQVRUWKHDIIHFWHGVXSSRUWHGV\VWHP/&2V

VKDOOEHGHFODUHGQRWPHW

FRQWLQXHG

6'0

DWWV%DU8QLW

$PHQGPHQW

5($&7,9,7<&21752/6<67(06

6+87'2:10$5*,16'0

/&2

$33/,&$%,/,7<

6'0VKDOOEHZLWKLQWKHOLPLWVVSHFLILHGLQWKH&2/5

02'(ZLWKNHII

02'(6DQG

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

6'0QRWZLWKLQOLPLWV

$

,QLWLDWHERUDWLRQWRUHVWRUH

6'0WRZLWKLQOLPLWV

PLQXWHV

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

9HULI\6'0WREHZLWKLQWKHOLPLWVVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

'(/(7('

DWWV%DU8QLW

$PHQGPHQW

5($&7,9,7<&21752/6<67(06

'(/(7('

&RUH 5HDFWLYLW\

DWWV%DU8QLW

$PHQGPHQW

5($&7,9,7<&21752/6<67(06

&RUH5HDFWLYLW\

/&2

7KHPHDVXUHGFRUHUHDFWLYLW\VKDOOEHZLWKLQ'NNRISUHGLFWHGYDOXHV

$33/,&$%,/,7<

02'(6DQG

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

0HDVXUHGFRUHUHDFWLYLW\QRW ZLWKLQOLPLW

$

5HHYDOXDWHFRUHGHVLJQDQG VDIHW\DQDO\VLVDQG

GHWHUPLQHWKDWWKHUHDFWRU

FRUHLVDFFHSWDEOHIRU

FRQWLQXHGRSHUDWLRQ

$1'

$

(VWDEOLVKDSSURSULDWHRSHUDWLQJ UHVWULFWLRQVDQG65V

GD\V

%

5HTXLUHG$FWLRQDQG DVVRFLDWHG&RPSOHWLRQ7LPH QRWPHW

%

%HLQ02'(

KRXUV

&RUH 5HDFWLYLW\

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

127(

7KHSUHGLFWHGUHDFWLYLW\YDOXHVPD\EHDGMXVWHG

QRUPDOL]HGWRFRUUHVSRQGWRWKHPHDVXUHGFRUH

UHDFWLYLW\SULRUWRH[FHHGLQJDIXHOEXUQXSRI

HIIHFWLYHIXOOSRZHUGD\V()3'DIWHUHDFKIXHO

ORDGLQJ

9HULI\PHDVXUHGFRUHUHDFWLYLW\LVZLWKLQ'NNRI

SUHGLFWHGYDOXHV

2QFHSULRUWR

HQWHULQJ02'(

DIWHUHDFKUHIXHOLQJ

$1'

127(

2QO\UHTXLUHGDIWHU

()3'

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

07&

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

9HULI\07&LVZLWKLQXSSHUOLPLW

3ULRUWRHQWHULQJ

02'(DIWHU

HDFKUHIXHOLQJ

65

'(/(7('

FRQWLQXHG

07&

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176FRQWLQXHG

6859(,//$1&(

)5(48(1&<

65

127(6

1RWUHTXLUHGWREHSHUIRUPHGXQWLOHIIHFWLYHIXOO SRZHUGD\V()3'DIWHUUHDFKLQJWKHHTXLYDOHQW RIDQHTXLOLEULXP573DOOURGVRXW$52ERURQ FRQFHQWUDWLRQRISSP

,IWKH07&LVPRUHQHJDWLYHWKDQWKHSSP 6XUYHLOODQFHOLPLWQRW/&2OLPLWVSHFLILHGLQWKH

&2/565VKDOOEHUHSHDWHGRQFHSHU

()3'GXULQJWKHUHPDLQGHURIWKHIXHOF\FOH

65QHHGQRWEHUHSHDWHGLIWKH07&

PHDVXUHGDWWKHHTXLYDOHQWRIHTXLOLEULXP 573$52ERURQFRQFHQWUDWLRQRISSPLVOHVV QHJDWLYHWKDQWKHSSP6XUYHLOODQFHOLPLW VSHFLILHGLQWKH&2/5

9HULI\07&LVZLWKLQORZHUOLPLW

2QFHHDFKF\FOH

5RG*URXS$OLJQPHQW/LPLWV

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

'

0RUHWKDQRQHURGQRWZLWKLQ DOLJQPHQWOLPLW

'

9HULI\6'0LVZLWKLQWKHOLPLWV VSHFLILHGLQWKH&2/5

25

'

,QLWLDWHERUDWLRQWRUHVWRUH UHTXLUHG6'0WRZLWKLQOLPLW

$1'

'

%HLQ02'(

KRXU

KRXUV

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

127(6

1RWUHTXLUHGWREHSHUIRUPHGIRUURGVDVVRFLDWHG ZLWKLQRSHUDEOHURGSRVLWLRQLQGLFDWRURUGHPDQG SRVLWLRQLQGLFDWRU

1RWUHTXLUHGWREHSHUIRUPHGXQWLOKRXUDIWHU DVVRFLDWHGURGPRWLRQ

9HULI\SRVLWLRQRILQGLYLGXDOURGVZLWKLQDOLJQPHQWOLPLW

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

65

9HULI\URGIUHHGRPRIPRYHPHQWWULSSDELOLW\E\

PRYLQJHDFKURGQRWIXOO\LQVHUWHGLQWKHFRUH

tVWHSVLQHLWKHUGLUHFWLRQ

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

FRQWLQXHG

&RQWURO%DQN,QVHUWLRQ/LPLWV

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

9HULI\HVWLPDWHGFULWLFDOFRQWUROEDQNSRVLWLRQLVZLWKLQ

WKHOLPLWVVSHFLILHGLQWKH&2/5

LWKLQKRXUVSULRU

WRDFKLHYLQJFULWLFDOLW\

65

127(

1RWUHTXLUHGWREHSHUIRUPHGXQWLOKRXUDIWHU

DVVRFLDWHGURGPRWLRQ

9HULI\HDFKFRQWUROEDQNLQVHUWLRQLVZLWKLQWKHLQVHUWLRQ

OLPLWVVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

65

127(

1RWUHTXLUHGWREHSHUIRUPHGXQWLOKRXUDIWHU

DVVRFLDWHGURGPRWLRQ

9HULI\VHTXHQFHDQGRYHUODSOLPLWVVSHFLILHGLQWKH

&2/5DUHPHWIRUFRQWUROEDQNVQRWIXOO\ZLWKGUDZQIURP

WKHFRUH

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

'(/(7('

DWWV%DU8QLW

$PHQGPHQW

5($&7,9,7<&21752/6<67(06

'(/(7('

3+<6,&67(676([FHSWLRQV02'(

DWWV%DU8QLW

$PHQGPHQW

5($&7,9,7<&21752/6<67(06

3+<6,&67(676([FHSWLRQV02'(

/&2

'XULQJWKHSHUIRUPDQFHRI3+<6,&67(676WKHUHTXLUHPHQWVRI

/&20RGHUDWRU7HPSHUDWXUH&RHIILFLHQW07&

/&25RG*URXS$OLJQPHQW/LPLWV

/&26KXWGRZQ%DQN,QVHUWLRQ/LPLWV

/&2&RQWURO%DQN,QVHUWLRQ/LPLWVDQG

/&25&60LQLPXP7HPSHUDWXUHIRU&ULWLFDOLW\

PD\EHVXVSHQGHGDQGWKHQXPEHURIUHTXLUHGFKDQQHOVIRU/&2

³576,QVWUXPHQWDWLRQ')XQFWLRQVDQGHPD\EHUHGXFHGWR

UHTXLUHGFKDQQHOVSURYLGHG

D

5&6ORZHVWORRSDYHUDJHWHPSHUDWXUHLVtq)

E

6'0LVZLWKLQWKHOLPLWVVSHFLILHGLQWKH&2/5DQG F

7+(50$/32:(5LV573

$33/,&$%,/,7<

'XULQJ3+<6,&67(676LQLWLDWHGLQ02'(

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

6'0QRWZLWKLQOLPLW

$

,QLWLDWHERUDWLRQWRUHVWRUH6'0

WRZLWKLQOLPLW

$1'

$

6XVSHQG3+<6,&67(676

H[FHSWLRQV

PLQXWHV

KRXU

%

7+(50$/32:(5QRW ZLWKLQOLPLW

%

2SHQUHDFWRUWULSEUHDNHUV

,PPHGLDWHO\

FRQWLQXHG

3+<6,&67(676([FHSWLRQV02'(

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

&

5&6ORZHVWORRSDYHUDJH WHPSHUDWXUHQRWZLWKLQOLPLW

&

5HVWRUH5&6ORZHVWORRS DYHUDJHWHPSHUDWXUHWRZLWKLQ

OLPLW

PLQXWHV

'

5HTXLUHG$FWLRQDQG DVVRFLDWHG&RPSOHWLRQ7LPH RI&RQGLWLRQ&QRWPHW

'

%HLQ02'(

PLQXWHV

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

3HUIRUPD&+$11(/23(5$7,21$/7(67RQSRZHUUDQJH

DQGLQWHUPHGLDWHUDQJHFKDQQHOVSHU6565

DQG7DEOH

3ULRUWRLQLWLDWLRQRI

3+<6,&67(676

65

9HULI\WKH5&6ORZHVWORRSDYHUDJHWHPSHUDWXUHLVtq)

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

9HULI\7+(50$/32:(5LV573

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

9HULI\6'0LVZLWKLQWKHOLPLWVVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

)4=

DWWV%DU8QLW

$PHQGPHQW

32:(5',675,%87,21/,0,76

+HDW)OX[+RW&KDQQHO)DFWRU)4=

/&2

)4=DVDSSUR[LPDWHGE\)4&=DQG)4:=VKDOOEHZLWKLQWKHOLPLWVVSHFLILHGLQ

WKH&2/5

$33/,&$%,/,7<

02'(

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

127(

5HTXLUHG$FWLRQ$VKDOOEH FRPSOHWHGZKHQHYHUWKLV

&RQGLWLRQLVHQWHUHGSULRUWR LQFUHDVLQJ7+(50$/

32:(5DERYHWKHOLPLWRI 5HTXLUHG$FWLRQ$65

LVQRWUHTXLUHGWREH SHUIRUPHGLIWKLV&RQGLWLRQLV HQWHUHGSULRUWR7+(50$/

32:(5H[FHHGLQJ573 DIWHUDUHIXHOLQJ

)4&=QRWZLWKLQOLPLW

$

5HGXFH7+(50$/32:(5

t573IRUHDFK

)4&=H[FHHGVOLPLW

$1'

$

5HGXFH3RZHU5DQJH

1HXWURQ)OX[²+LJKWULS

VHWSRLQWV!IRUHDFK

WKDW7+(50$/32:(5

LVOLPLWHGEHORZ5$7('

7+(50$/32:(5E\

5HTXLUHG$FWLRQ$

$1'

$

5HGXFH2YHUSRZHU7WULS

VHWSRLQWVtIRUHDFK

WKDW7+(50$/32:(5LV

OLPLWHGEHORZ5$7('

7+(50$/32:(5E\

5HTXLUHG$FWLRQ$

$1'

PLQXWHVDIWHU

HDFK)4&=

GHWHUPLQDWLRQ

KRXUVDIWHUHDFK

)4&=GHWHUPLQDWLRQ

KRXUVDIWHUHDFK

)4&=GHWHUPLQDWLRQ

FRQWLQXHG

)4=

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21

5(48,5('$&7,21

&203/(7,217,0(

$ FRQWLQXHG

$

3HUIRUP65DQG65

3ULRUWRLQFUHDVLQJ

7+(50$/32:(5

DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ$

%

)4:=QRWZLWKLQOLPLWV

%

,PSOHPHQWD5$2&RSHUDWLQJ VSDFHVSHFLILHGLQWKH&2/5

WKDWUHVWRUHV)4:=WRZLWKLQ

OLPLWV

$1'

%3HUIRUP65DQG

65LIFRQWUROURGPRWLRQ

LVUHTXLUHGWRFRPSO\ZLWKWKH

QHZRSHUDWLQJVSDFH

25

%127(

5HTXLUHG$FWLRQ%VKDOOEH

FRPSOHWHGZKHQHYHU5HTXLUHG

$FWLRQ%LVSHUIRUPHGSULRU

WRLQFUHDVLQJ7+(50$/

32:(5DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ%

/LPLW7+(50$/32:(5WR

OHVVWKDQ5$7('7+(50$/

32:(5DQGUHGXFH$)'

OLPLWVDVVSHFLILHGLQWKH

&2/5

$1'

%5HGXFH3RZHU5DQJH1HXWURQ

)OX[+/-+LJKWULSVHWSRLQWV

IRUHDFKWKDW7+(50$/

32:(5LVOLPLWHGEHORZ

5$7('7+(50$/32:(5

E\5HTXLUHG$FWLRQ%

$1'

KRXUV

KRXUVDIWHUHDFK

)4:=GHWHUPLQDWLRQ

KRXUVDIWHUHDFK

)4:=GHWHUPLQDWLRQ

FRQWLQXHG

)4=

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

% FRQWLQXHG

%5HGXFH2YHUSRZHU7WULS VHWSRLQWVIRUHDFK

WKDW7+(50$/32:(5LV

OLPLWHGEHORZ5$7('

7+(50$/32:(5E\

5HTXLUHG$FWLRQ%

$1'

%3HUIRUP65DQG65

KRXUVDIWHUHDFK

)4:=GHWHUPLQDWLRQ

3ULRUWRLQFUHDVLQJ

7+(50$/32:(5

DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ

%

&

5HTXLUHG$FWLRQDQG DVVRFLDWHG&RPSOHWLRQ7LPH QRWPHW

&

%HLQ02'(

KRXUV

$)'

DWWV%DU8QLW

$PHQGPHQW

32:(5',675,%87,21/,0,76

$;,$/)/8;',))(5(1&($)'

/&2

7KH$)'LQIOX[GLIIHUHQFHXQLWVVKDOOEHPDLQWDLQHGZLWKLQWKHOLPLWVVSHFLILHGLQ

WKH&2/5

127(

7KH$)'VKDOOEHFRQVLGHUHGRXWVLGHOLPLWVZKHQWZRRUPRUH23(5$%/(H[FRUH

FKDQQHOVLQGLFDWH$)'WREHRXWVLGHOLPLWV

$33/,&$%,/,7<

02'(ZLWK7+(50$/32:(5!573

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

$)'QRWZLWKLQOLPLWV

$

5HGXFH7+(50$/32:(5WR

573

PLQXWHV

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

9HULI\$)'ZLWKLQOLPLWVIRUHDFK23(5$%/(H[FRUH

FKDQQHO

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

4375

DWWV%DU8QLW

$PHQGPHQW

32:(5',675,%87,21/,0,76

48$'5$1732:(57,/75$7,24375

/&2

7KH4375VKDOOEHd

$33/,&$%,/,7<

02'(ZLWK7+(50$/32:(5!573

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

4375QRWZLWKLQOLPLW

$

$1'

$

$1'

$

$1'

$

5HGXFH7+(50$/32:(5t

IURP573IRUHDFKRI

4375!

'HWHUPLQH4375

3HUIRUP65DQG

65

5HHYDOXDWHVDIHW\DQDO\VHV

DQGFRQILUPUHVXOWVUHPDLQ

YDOLGIRUGXUDWLRQRIRSHUDWLRQ

XQGHUWKLVFRQGLWLRQ

$1'

KRXUVDIWHUHDFK

4375GHWHUPLQDWLRQ

2QFHSHUKRXUV

KRXUVDIWHU

DFKLHYLQJHTXLOLEULXP

FRQGLWLRQVIURPD

7+(50$/32:(5

UHGXFWLRQSHU

5HTXLUHG$FWLRQ$

$1'

2QFHSHUGD\V

WKHUHDIWHU

3ULRUWRLQFUHDVLQJ

7+(50$/32:(5

DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ$

FRQWLQXHG

4375

DWWV%DU8QLW

$PHQGPHQW

$&7,216

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

FRQWLQXHG

$

127(6

3HUIRUP5HTXLUHG

$FWLRQ$RQO\DIWHU 5HTXLUHG$FWLRQ$LV FRPSOHWHG

5HTXLUHG$FWLRQ$VKDOO EHFRPSOHWHGZKHQHYHU 5HTXLUHG$FWLRQ$LV SHUIRUPHG

1RUPDOL]HH[FRUHGHWHFWRUVWR

UHVWRUH4375WRZLWKLQOLPLW

$1'

$

127(

3HUIRUP5HTXLUHG$FWLRQ$

RQO\DIWHU5HTXLUHG$FWLRQ$

LVFRPSOHWHG

3HUIRUP65DQG

65

3ULRUWRLQFUHDVLQJ

7+(50$/32:(5

DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ$

LWKLQKRXUVDIWHU

DFKLHYLQJHTXLOLEULXP

FRQGLWLRQVDW573QRW

WRH[FHHGKRXUV

DIWHULQFUHDVLQJ

7+(50$/32:(5

DERYHWKHOLPLWRI

5HTXLUHG$FWLRQ$

%

5HTXLUHG$FWLRQDQG DVVRFLDWHG&RPSOHWLRQ7LPH QRWPHW

%

5HGXFH7+(50$/32:(5WR

d573

KRXUV

4375

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

127(6

LWKLQSXWIURPRQHSRZHUUDQJHQHXWURQIOX[

FKDQQHOLQRSHUDEOHDQG7+(50$/32:(5

573WKHUHPDLQLQJWKUHHSRZHUUDQJH FKDQQHOVFDQEHXVHGIRUFDOFXODWLQJ4375

65PD\EHSHUIRUPHGLQOLHXRIWKLV 6XUYHLOODQFH

9HULI\4375LVZLWKLQOLPLWE\FDOFXODWLRQ

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

65

127(

1RWUHTXLUHGWREHSHUIRUPHGXQWLOKRXUVDIWHULQSXW

WR4375IURPRQHRUPRUHSRZHUUDQJHQHXWURQIOX[

FKDQQHOVDUHLQRSHUDEOHZLWK7+(50$/32:(5

573

9HULI\4375LVZLWKLQOLPLWXVLQJHLWKHUWKHPRYDEOH

LQFRUHGHWHFWRUVRUWKH3'06

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

,167580(17$7,21

5HDFWRU7ULS6\VWHP576,QVWUXPHQWDWLRQ

/&2

7KH576LQVWUXPHQWDWLRQIRUHDFK)XQFWLRQLQ7DEOHVKDOOEH23(5$%/(

$33/,&$%,/,7<

$FFRUGLQJWR7DEOH

$&7,216

127(

6HSDUDWH&RQGLWLRQHQWU\LVDOORZHGIRUHDFK)XQFWLRQ

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

$

2QHRUPRUH)XQFWLRQVZLWK RQHRUPRUHUHTXLUHGFKDQQHOV RUWUDLQVLQRSHUDEOH

$

(QWHUWKH&RQGLWLRQUHIHUHQFHG

LQ7DEOHIRUWKH

FKDQQHOVRUWUDLQV

,PPHGLDWHO\

%

2QH0DQXDO5HDFWRU7ULS FKDQQHOLQRSHUDEOH

%

5HVWRUHFKDQQHOWR

23(5$%/(VWDWXV

25

%%HLQ02'(

KRXUV

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

&

2QHFKDQQHORUWUDLQ LQRSHUDEOH

&

5HVWRUHFKDQQHORUWUDLQWR 23(5$%/(VWDWXV

25

&,QLWLDWHDFWLRQWRIXOO\LQVHUWDOO URGV

$1'

&3ODFHWKH5RG&RQWURO6\VWHP LQDFRQGLWLRQLQFDSDEOHRIURG

ZLWKGUDZDO

KRXUV

'

2QH3RZHU5DQJH1HXWURQ

)OX[+LJKFKDQQHO LQRSHUDEOH

127(

7KHLQRSHUDEOHFKDQQHOPD\EH E\SDVVHGIRUXSWRKRXUVIRU VXUYHLOODQFHWHVWLQJDQGVHWSRLQW DGMXVWPHQWRIRWKHUFKDQQHOV

3HUIRUP65LILQSXWWR 4375IURPRQHRUPRUH3RZHU 5DQJH1HXWURQ)OX[FKDQQHOVDUH LQRSHUDEOHZLWK7+(50$/

32:(5573

'

3ODFHFKDQQHOLQWULS

25

'

%HLQ02'(

KRXUV

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

(

2QHFKDQQHOLQRSHUDEOH

127(

7KHLQRSHUDEOHFKDQQHOPD\EH

E\SDVVHGIRUXSWRKRXUV

IRUVXUYHLOODQFHWHVWLQJRIRWKHU

FKDQQHOV

(

3ODFHFKDQQHOLQWULS

25

(

%HLQ02'(

KRXUV

)

2QH,QWHUPHGLDWH5DQJH 1HXWURQ)OX[FKDQQHO LQRSHUDEOH

)

5HGXFH7+(50$/32:(5 WR3

25

)

,QFUHDVH7+(50$/

32:(5WR!3

KRXUV

7ZR,QWHUPHGLDWH5DQJH 1HXWURQ)OX[FKDQQHOV LQRSHUDEOH

6XVSHQGRSHUDWLRQV

LQYROYLQJSRVLWLYHUHDFWLYLW\

DGGLWLRQV

$1'

5HGXFH7+(50$/32:(5

WR3

,PPHGLDWHO\

KRXUV

+

'(/(7('

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

,

2QH6RXUFH5DQJH1HXWURQ

)OX[FKDQQHOLQRSHUDEOH

,

6XVSHQGRSHUDWLRQVLQYROYLQJ

SRVLWLYHUHDFWLYLW\DGGLWLRQV

,PPHGLDWHO\

-

7ZR6RXUFH5DQJH1HXWURQ

)OX[FKDQQHOVLQRSHUDEOH

-

2SHQUHDFWRUWULSEUHDNHUV

57%V

,PPHGLDWHO\

.

2QH6RXUFH5DQJH1HXWURQ

)OX[FKDQQHOLQRSHUDEOH

.

5HVWRUHFKDQQHOWR

23(5$%/(VWDWXV

25

.

,QLWLDWHDFWLRQWRIXOO\LQVHUWDOO URGV

$1'

.3ODFHWKH5RG&RQWURO6\VWHP LQDFRQGLWLRQLQFDSDEOHRIURG

ZLWKGUDZDO

KRXUV

/

5HTXLUHG6RXUFH5DQJH 1HXWURQ)OX[FKDQQHO LQRSHUDEOH

/

6XVSHQGRSHUDWLRQVLQYROYLQJ

SRVLWLYHUHDFWLYLW\DGGLWLRQV

$1'

/

&ORVHXQERUDWHGZDWHUVRXUFH

LVRODWLRQYDOYHV

$1'

/

3HUIRUP65

,PPHGLDWHO\

KRXU

$1'

2QFHSHU

KRXUVWKHUHDIWHU

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

4

2QH57%WUDLQLQRSHUDEOH

127(

2QHWUDLQPD\EHE\SDVVHGIRUXSWR

KRXUVIRUVXUYHLOODQFHWHVWLQJ

SURYLGHGWKHRWKHUWUDLQLV23(5$%/(

4 5HVWRUHWUDLQWR23(5$%/(

VWDWXV

25

4 %HLQ02'(

KRXUV

5

2QHRUPRUHFKDQQHOV LQRSHUDEOH

5

9HULI\LQWHUORFNLV LQUHTXLUHGVWDWHIRUH[LVWLQJXQLW

FRQGLWLRQV

25

5 %HLQ02'(

KRXU

KRXUV

6

2QHRUPRUHFKDQQHOV LQRSHUDEOH

6 9HULI\LQWHUORFNLV LQUHTXLUHGVWDWHIRUH[LVWLQJXQLW

FRQGLWLRQV

25

6 %HLQ02'(

KRXU

KRXUV

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,21 7,0(

7

2QHWULSPHFKDQLVP LQRSHUDEOHIRURQH 57%

7

5HVWRUHLQRSHUDEOHWULS

PHFKDQLVPWR23(5$%/(

VWDWXV

25

7

%HLQ02'(

KRXUV

8

2QH6WHDP*HQHUDWRU:DWHU

/HYHO/RZ/RZFKDQQHO LQRSHUDEOH

127(

2QHFKDQQHOPD\EHE\SDVVHG

IRUXSWRKRXUVIRUVXUYHLOODQFH

WHVWLQJ

8

3ODFHFKDQQHOLQWULS

$1'

8

)RUWKHDIIHFWHGSURWHFWLRQVHW

VHWWKH7ULS7LPH'HOD\7VWR

PDWFKWKH7ULS7LPH'HOD\

7P

25

8

%HLQ02'(

KRXUV

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21 5(48,5('$&7,21

&203/(7,217,0(

9

2QH9HVVHO'7FKDQQHO LQRSHUDEOH

127(

2QHFKDQQHOPD\EHE\SDVVHG IRUXS WR KRXUVIRUVXUYHLOODQFHWHVWLQJ

9

6HWWKH7ULS7LPH'HOD\

WKUHVKROGSRZHUOHYHOIRU7V

DQG7PWRSRZHU

25 9

%HLQ02'(

KRXUV

2QHFKDQQHO LQRSHUDEOH

127(

2QHFKDQQHOPD\EHE\SDVVHG IRUXSWR KRXUVIRUVXUYHLOODQFH

WHVWLQJ

3ODFHFKDQQHOLQWULS

25

%HLQ02'(

KRXUV

2QHFKDQQHO LQRSHUDEOH

127(

2QHFKDQQHOPD\EHE\SDVVHG IRUXS WR KRXUVIRUVXUYHLOODQFHWHVWLQJ

3ODFHFKDQQHOLQWULS

25

5HGXFH7+(50$/32:(5WR

3

KRXUV

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216FRQWLQXHG

&21',7,21

5(48,5('$&7,21

&203/(7,217,0(

<

2QHWZRRUWKUHH7XUELQH 6WRS9DOYH&ORVXUHFKDQQHOV LQRSHUDEOH

<

3ODFHFKDQQHOVLQWULS

25

<

5HGXFH7+(50$/32:(5WR

3

KRXUV

6859(,//$1&(5(48,5(0(176

127(

5HIHUWR7DEOHWRGHWHUPLQHZKLFK65VDSSO\IRUHDFK576)XQFWLRQ

6859(,//$1&(

)5(48(1&<

65

3HUIRUP&+$11(/&+(&.

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

127(6

$GMXVW1,6FKDQQHOLIDEVROXWHGLIIHUHQFHLV!

5HTXLUHGWREHSHUIRUPHGZLWKLQKRXUVDIWHU 7+(50$/32:(5LVt573

&RPSDUHUHVXOWVRIFDORULPHWULFKHDW

EDODQFHFDOFXODWLRQWR1XFOHDU

,QVWUXPHQWDWLRQ6\VWHP1,6FKDQQHO

RXWSXW

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

FRQWLQXHG

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation

)81&7,21

$33/,&$%/(02'(6

2527+(5

63(&,),('

&21',7,216

5(48,5('

&+$11(/6

&21',7,216

6859(,//$1&(

5(48,5(0(176

$//2:$%/(

9$/8(

120,1$/

75,3

6(732,17

0DQXDO5HDFWRU

%

65

1$

7ULS

DDD

65

1$

3RZHU5DQJH 1HXWURQ )OX[

D

+LJK

'

65

d

573

65

573

65

E

/RZ

E

(

65

d573

573

65

3RZHU5DQJH 1HXWURQ)OX[5DWH D

+LJK3RVLWLYH

(

65

d573

573ZLWK

5DWH 65

ZLWKWLPH

WLPH

FRQVWDQW

tVHF

E

+LJK1HJDWLYH 5DWH'HOHWHG

,QWHUPHGLDWH5DQJH

EF

)*

65

d573

573

1HXWURQ)OX[

65

FRQWLQXHG

D

LWK5RG&RQWURO6\VWHPFDSDEOHRIURGZLWKGUDZDORURQHRUPRUHURGVQRWIXOO\LQVHUWHG

E

%HORZWKH33RZHU5DQJH1HXWURQ)OX[LQWHUORFNV

F

$ERYHWKH3,QWHUPHGLDWH5DQJH1HXWURQ)OX[LQWHUORFNV

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

Table 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation

)81&7,21

$33/,&$%/(02'(6

2527+(5

63(&,),('

&21',7,216

5(48,5('

&+$11(/6

&21',7,216

6859(,//$1&(

5(48,5(0(176

$//2:$%/(

9$/8(

120,1$/

75,3

6(732,17

6RXUFH5DQJH

G

,-

65

d(

(FSV

1HXWURQ)OX[

65

FSV

65

DDD

-.

65

d(

(FSV

65

FSV

65

HHH

/

65

1$

65

2YHUWHPSHUDWXUH'7

65

5HIHUWR

65

1RWH

65

3DJH

65

2YHUSRZHU'7

65

5HIHUWR

65

1RWH

65

3DJH

65

3UHVVXUL]HU 3UHVVXUH D

/RZ

I

65

t

SVLJ

65

SVLJ 65

65

E

+LJK

65

d

SVLJ

65

SVLJ 65

65

FRQWLQXHG

D

LWK5RG&RQWURO6\VWHPFDSDEOHRIURGZLWKGUDZDORURQHRUPRUHURGVQRWIXOO\LQVHUWHG

G

%HORZWKH3,QWHUPHGLDWH5DQJH1HXWURQ)OX[LQWHUORFNV

H

LWKWKH57%VRSHQ,QWKLVFRQGLWLRQVRXUFHUDQJH)XQFWLRQGRHVQRWSURYLGHUHDFWRUWULSEXWGRHVSURYLGHLQGLFDWLRQ

I

$ERYHWKH3/RZ3RZHU5HDFWRU7ULSV%ORFNLQWHUORFN

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

Table 3.3.1-1 (page 6 of 9)

Reactor Trip System Instrumentation

)81&7,21

$33/,&$%/(02'(6

2527+(5

63(&,),('

&21',7,216

5(48,5('

&+$11(/6

&21',7,216

6859(,//$1&(

5(48,5(0(176

$//2:$%/(

9$/8(

120,1$/

75,3

6(732,17

5HDFWRU7ULS

WUDLQV

4

65

1$

%UHDNHUVM57%V

DDD

WUDLQV

&

65

1$

5HDFWRU7ULS

HDFK

7

65

1$

%UHDNHU SHU57%

8QGHUYROWDJH DQG 6KXQW7ULS

DDD

HDFK

&

65

1$

0HFKDQLVPV SHU57%

$XWRPDWLF7ULS

WUDLQV

3

65

1$

/RJLF

DDD

WUDLQV

&

65

1$

D

LWK5RG&RQWURO6\VWHPFDSDEOHRIURGZLWKGUDZDORURQHRUPRUHURGVQRWIXOO\LQVHUWHG

M

,QFOXGLQJDQ\UHDFWRUWULSE\SDVVEUHDNHUVWKDWDUHUDFNHGLQDQGFORVHGIRUE\SDVVLQJDQ57%

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

Table 3.3.1-1 (page 7 of 9)

Reactor Trip System Instrumentation 1RWH2YHUWHPSHUDWXUH'7

7KH2YHUWHPSHUDWXUH'7)XQFWLRQ$OORZDEOH9DOXHVKDOOQRWH[FHHGWKHIROORZLQJ7ULS6HWSRLQWE\PRUH

WKDQRI'7VSDQ

¿ 3/4 1/2

c

W

d

¿ 3/4 1/2

W

)I

(

f

)

P P

(

K T

T

)s 1(

K K

T s

1 s

1 T

1 3

2 1

0 5

4

KHUH

'7LVPHDVXUHG5&6'7)

'72LVWKHLQGLFDWHG'7DW573)

VLVWKH/DSODFHWUDQVIRUPRSHUDWRUVHF

7LVWKHPHDVXUHG5&6DYHUDJHWHPSHUDWXUH)

7

LVWKHLQGLFDWHG7DYJDW573d

3LVWKHPHDVXUHGSUHVVXUL]HUSUHVVXUHSVLJ

3

LVWKHQRPLQDO5&6RSHUDWLQJSUHVVXUHt SVLJ

.d

.t )

. SVLJ

Wt VHF

Wd VHF

Wt VHF

Wd VHF

I', ^ TWTE`

ZKHQTWTE 573

RI573

ZKHQ 573dTWTEd 573

^T WTE `

ZKHQTWTE! 573

KHUHTWDQGTEDUHSHUFHQW573LQWKHXSSHUDQGORZHUKDOYHVRIWKHFRUH

UHVSHFWLYHO\DQGTWTELVWKHWRWDO7+(50$/32:(5LQSHUFHQW573

7KHVHYDOXHVGHQRWHGZLWK DUHVSHFLILHGLQWKH&2/5

576,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

Table 3.3.1-1 (page 8 of 9)

Reactor Trip System Instrumentation 1RWH2YHUSRZHU'7

7KH2YHUSRZHU'7)XQFWLRQ$OORZDEOH9DOXHVKDOOQRWH[FHHGWKHIROORZLQJ7ULS6HWSRLQWE\PRUHWKDQRI'7

VSDQ

¿ 3/4 1/2

¸¸

¹

¨¨

©

§ W

W

d

¸¸

¹

¨¨

©

§ W

W

)I

(

f T

T K

T s

1 s

K K

T s

1 s

1 T

2 6

3 3

5 4

0 5

4

KHUH

'7LVPHDVXUHG5&6'7q)

'72LVWKHLQGLFDWHG'7DW573q)

VLVWKH/DSODFHWUDQVIRUPRSHUDWRUVHF

7LVWKHPHDVXUHG5&6DYHUDJHWHPSHUDWXUHq)

7LVWKHLQGLFDWHG7DYJDW573d q)

.d

.t q)IRULQFUHDVLQJ7DYJ

.t )ZKHQ7!7

q)IRUGHFUHDVLQJ7DYJ

)ZKHQ7d7

Wt VHF

Wd VHF

I',

7KHVHYDOXHVGHQRWHGZLWK DUHVSHFLILHGLQWKH&2/5

(6)$6,QVWUXPHQWDWLRQ

DWWV%DU8QLW

$PHQGPHQW

$&7,216

&21',7,21

5(48,5('$&7,21

&203/(7,217,0(

.

FRQWLQXHG

. %HLQ02'(

$1'

. %HLQ02'(

KRXUV

/

2QHRUPRUHFKDQQHOV LQRSHUDEOH

/

9HULI\LQWHUORFNLVLQUHTXLUHG

VWDWHIRUH[LVWLQJXQLWFRQGLWLRQ

25

/

%HLQ02'(

$1'

/

%HLQ02'(

KRXU

KRXUV

FRQWLQXHG

5&63UHVVXUH7HPSHUDWXUHDQG)ORZ'1%/LPLWV

DWWV%DU8QLW

$PHQGPHQW

5($&725&22/$176<67(05&6

5&63UHVVXUH7HPSHUDWXUHDQG)ORZ'HSDUWXUHIURP1XFOHDWH%RLOLQJ'1%/LPLWV

/&2

5&6'1%SDUDPHWHUVIRUSUHVVXUL]HUSUHVVXUH5&6DYHUDJHWHPSHUDWXUHDQG

5&6WRWDOIORZUDWHVKDOOEHZLWKLQWKHOLPLWVVSHFLILHGEHORZ

D

3UHVVXUL]HUSUHVVXUHLVJUHDWHUWKDQRUHTXDOWRWKHOLPLWVSHFLILHGLQWKH

&2/5

E

5&6DYHUDJHWHPSHUDWXUHLVOHVVWKDQRUHTXDOWRWKHOLPLWVSHFLILHGLQWKH

&2/5DQG F

5&6WRWDOIORZUDWHtJSPSURFHVVFRPSXWHURUFRQWUROERDUG LQGLFDWLRQDQGJUHDWHUWKDQRUHTXDOWRWKHOLPLWVSHFLILHGLQWKH&2/5

$33/,&$%,/,7<

02'(

127(

3UHVVXUL]HUSUHVVXUHOLPLWGRHVQRWDSSO\GXULQJ

D

7+(50$/32:(5UDPS!573SHUPLQXWHRU E

7+(50$/32:(5VWHS!573

$&7,216

&21',7,21

5(48,5('$&7,21

&203/(7,217,0(

$

2QHRUPRUH5&6'1%

SDUDPHWHUVQRWZLWKLQOLPLWV

$

5HVWRUH5&6'1%

SDUDPHWHUVWRZLWKLQOLPLW

KRXUV

%

5HTXLUHG$FWLRQDQG DVVRFLDWHG&RPSOHWLRQ7LPH QRWPHW

%

%HLQ02'(

KRXUV

5&63UHVVXUH7HPSHUDWXUHDQG)ORZ'1%/LPLWV

DWWV%DU8QLW

$PHQGPHQW

6859(,//$1&(5(48,5(0(176

6859(,//$1&(

)5(48(1&<

65

9HULI\SUHVVXUL]HUSUHVVXUHLVJUHDWHUWKDQRUHTXDOWR

WKHOLPLWVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

9HULI\5&6DYHUDJHWHPSHUDWXUHLVOHVVWKDQRUHTXDO

WRWKHOLPLWVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

9HULI\5&6WRWDOIORZUDWHLVtJSPSURFHVV

FRPSXWHURUFRQWUROERDUGLQGLFDWLRQDQGJUHDWHUWKDQ

RUHTXDOWRWKHOLPLWVSHFLILHGLQWKH&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP 65

127(

5HTXLUHGWREHSHUIRUPHGZLWKLQKRXUVDIWHU

t573

9HULI\E\SUHFLVLRQKHDWEDODQFHRUHOERZWDS'S

PHWKRGWKDW5&6WRWDOIORZUDWHLVtJSP

DQGJUHDWHUWKDQRUHTXDOWRWKHOLPLWVSHFLILHGLQWKH

&2/5

,QDFFRUGDQFHZLWK

WKH6XUYHLOODQFH

)UHTXHQF\&RQWURO

3URJUDP

5HSRUWLQJ5HTXLUHPHQWV

FRQWLQXHG

DWWV%DU8QLW

$PHQGPHQW

5HSRUWLQJ5HTXLUHPHQWVFRQWLQXHG

&25(23(5$7,1*/,0,765(3257&2/5

D

&RUHRSHUDWLQJOLPLWVVKDOOEHHVWDEOLVKHGSULRUWRWKHLQLWLDODQGHDFKUHORDG F\FOHRUSULRUWRDQ\UHPDLQLQJSRUWLRQRIDF\FOHDQGVKDOOEHGRFXPHQWHGLQWKH

&2/5IRUWKHIROORZLQJ

/&2

6KXWGRZQ0DUJLQ

/&2

0RGHUDWRU7HPSHUDWXUH&RHIILFLHQW

/&2

5RG*URXS$OLJQPHQW/LPLWV

/&2

6KXWGRZQ%DQN,QVHUWLRQ/LPLW

/&2

&RQWURO%DQN,QVHUWLRQ/LPLWV

/&2

+HDW)OX[+RW&KDQQHO)DFWRU

/&2

1XFOHDU(QWKDOS\5LVH+RW&KDQQHO)DFWRU

/&2

$[LDO)OX['LIIHUHQFH

/&2

%RURQ&RQFHQWUDWLRQ

E

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

7KHDSSURYHGDQDO\WLFDOPHWKRGVDUHVSHFLILFDOO\WKRVHGHVFULEHGLQWKHIROORZLQJ GRFXPHQWV

&$33$:(67,1*+286(5(/2$'6$)(7<(9$/8$7,21 0(7+2'2/2*<'-XO\:3URSULHWDU\0HWKRGRORJ\IRU 6SHFLILFDWLRQV6KXWGRZQ0DUJLQ0RGHUDWRU7HPSHUDWXUH

&RHIILFLHQW5RG*URXS$OLJQPHQW/LPLWV6KXWGRZQ%DQN

,QVHUWLRQ/LPLW&RQWURO%DQN,QVHUWLRQ/LPLWV+HDW)OX[+RW

&KDQQHO)DFWRU1XFOHDU(QWKDOS\5LVH+RW&KDQQHO)DFWRU

$[LDO)OX['LIIHUHQFHDQG%RURQ&RQFHQWUDWLRQ

&$33$5HYLVLRQ³5HDOLVWLF/2&$(YDOXDWLRQ0HWKRGRORJ\

$SSOLHGWRWKH)XOO6SHFWUXPRI%UHDN6L]HV)8//63(&7580/2&$

0HWKRGRORJ\'1RYHPEHU

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. NPF-96

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated December 13, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-96 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 76 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: December 17, 2024 DAVID WRONA Digitally signed by DAVID WRONA Date: 2024.12.17 15:33:51 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 76 WATTS BAR NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE NO. NPF-96 DOCKET NO. 50-391 Replace page 3 of Facility Operating License No. NPF-96 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 2.0-1 2.0-1 2.0-2 3.0-3 3.0-3 3.1-1 3.1-1 3.1-2 3.1-2 3.1-3 3.1-3 3.1-4 3.1-4 3.1-6 3.1-6 3.1-9 3.1-9 3.1.13 3.1.13 3.1.14 3.1.14 3.1.14a 3.1-18 3.1-18 3.1-19 3.1-19a 3.1-20 3.1-19 3.1-21 3.1-20 3.2-3 3.2-3 3.2-4 3.2-4 3.2-8 3.2-8 3.2-9 3.2-9 3.2-10 3.2-10 3.2-11 3.2-11 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3-4 3.3-7 3.3-7 3.3-8 3.3-8 3.3-10 3.3-10 3.3-15 3.3-15 3.3-16 3.3-16 Remove Pages Insert Pages 3.3-20 3.3-20 3.3-21 3.3-21 3.3-22 3.3-22 3.3-29 3.3-29 3.4-1 3.4-1 3.4-2 3.4-2 5.0-30 5.0-30 5.0-31 5.0-31 Unit 2 Facility Operating License No. NPF-96 Amendment No. 76 C.

The license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.

(1)

Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 76 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

TVA shall implement permanent modifications to prevent overtopping of the embankments of the Fort Loudon Dam due to the Probable Maximum Flood by June 30, 2018.

(4)

FULL SPECTRUM LOCA Methodology shall be implemented when the WBN Unit 2 steam generators are replaced with steam generators equivalent to the existing steam generators at WBN Unit 1.

(5)

By December 31, 2019, the licensee shall report to the NRC that the actions to resolve the issues identified in Bulletin 2012-01, Design Vulnerability in Electrical Power System, have been implemented.

(6)

The licensee shall maintain in effect the provisions of the physical security plan, security personnel training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90 and 50.54(p).

(7)

TVA shall fully implement and maintain in effect all provisions of the Commission approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The TVA approved CSP was discussed in NUREG-0847, Supplement 28, as amended by changes approved in License Amendment No. 7.

(8)

TVA shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility, as described in NUREG-0847, Supplement 29, subject to the following provision:

SLs 2.0 2.0 SAFETY LIMITS (SLs)

Watts Bar - Unit 2 2.0-1 Amendment 76 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 1.14 for the WRB-2M DNB correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 9°F per 10,000 MWD/MTU of burnup.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

LCO Applicability 3.0 3.0 LCO APPLICABILITY Watts Bar - Unit 2 3.0-3 Amendment 6, 73, 76 LCO 3.0.7 Test Exception LCO 3.1.10 allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional.

When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and

a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or

b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the end of the specified period, the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

(continued)

SDM 3.1.1 Watts Bar - Unit 2 3.1-1 Amendment 36, 76 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 2 with keff < 1.0, MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits.

A.1 Initiate boration to restore SDM to within limits.

15 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within the limits specified in the COLR.

In accordance with the Surveillance Frequency Control Program

DELETED 3.1.2 Watts Bar - Unit 2 3.1-2 Amendment 36, 76 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 DELETED

Core Reactivity 3.1.3 Watts Bar - Unit 2 3.1-3 Amendment 76 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Core Reactivity LCO 3.1.3 The measured core reactivity shall be within +/- 1% k/k of predicted values.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity not within limit.

A.1 7 days AND A.2 Re-evaluate core design and safety analysis, and determine that the reactor core is acceptable for continued operation.

Establish appropriate operating restrictions and SRs.

7 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Core Reactivity 3.1.3 Watts Bar - Unit 2 3.1-4 Amendment 36, 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1

NOTE-------------------------------

The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading.

Verify measured core reactivity is within +/- 1% k/k of predicted values.

Once prior to entering MODE 1 after each refueling AND

NOTE---------

Only required after 60 EFPD In accordance with the Surveillance Frequency Control Program

MTC 3.1.4 Watts Bar - Unit 2 3.1-6 Amendment 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify MTC is within upper limit Prior to entering MODE 1 after each refueling SR 3.1.4.2 DELETED SR 3.1.4.3

NOTES----------------------------

1.

Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm.

2.

If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.4.3 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

3.

SR 3.1.4.3 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.

Verify MTC is within lower limit.

Once each cycle

Rod Group Alignment Limits 3.1.5 Watts Bar - Unit 2 3.1-9 Amendment 20, 36, 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1

NOTES----------------------------

1.

Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.

2.

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after associated rod motion.

Verify position of individual rods within alignment limit.

In accordance with the Surveillance Frequency Control Program SR 3.1.5.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.

In accordance with the Surveillance Frequency Control Program SR 3.1.5.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:

a.

Tavg 551F; and b.

All reactor coolant pumps operating.

Prior to criticality after each removal of the reactor head

Control Bank Insertion Limits 3.1.7 Watts Bar - Unit 2 3.1-13 Amendment 20, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Restore the control bank to within the insertion, sequence, and overlap limits specified in the COLR.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. Control bank insertion limits not met for reasons other than Condition A.

B.1.1 Verify SDM is within the limits specified in the COLR.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR B.1.2 Initiate boration to restore SDM to within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.2 Restore control bank(s) to within limits.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. Control bank sequence or overlap limits not met for reasons other than Condition A.

C.1.1 Verify SDM is within the limits specified in the COLR.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR C.1.2 Initiate boration to restore SDM to within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.2 Restore control bank sequence and overlap to within limits.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. Required Action and associated Completion Time not met.

D.1 Be in MODE 2 with keff 1.0.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Control Bank Insertion Limits 3.1.7 Watts Bar - Unit 2 3.1-14 Amendment 20, 36, 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify estimated critical control bank position is within the limits specified in the COLR.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality SR 3.1.7.2

NOTE-------------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after associated rod motion.

Verify each control bank insertion is within the insertion limits specified in the COLR.

In accordance with the Surveillance Frequency Control Program SR 3.1.7.3

NOTE-------------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after associated rod motion.

Verify sequence and overlap limits specified in the COLR are met for control banks not fully withdrawn from the core.

In accordance with the Surveillance Frequency Control Program

DELETED 3.1.9 Watts Bar-Unit 2 3.1-18 Amendment 36, 76 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 DELETED

PHYSICS TESTS Exceptions - MODE 2 3.1.10 Watts Bar - Unit 2 3.1-19 Amendment 76 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.10 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.4, "Moderator Temperature Coefficient (MTC)";

LCO 3.1.5, "Rod Group Alignment Limits";

LCO 3.1.6, "Shutdown Bank Insertion Limits";

LCO 3.1.7, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended, and the number of required channels for LCO 3.3.1, RTS Instrumentation, Functions 2, 3, 6, and 16.e, may be reduced to 3 required channels provided:

a.

RCS lowest loop average temperature is 541°F; b.

SDM is within the limits specified in the COLR; and c.

THERMAL POWER is 5% RTP.

APPLICABILITY:

During PHYSICS TESTS initiated in MODE 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit.

A.1 Initiate boration to restore SDM to within limit.

15 minutes AND A.2 Suspend PHYSICS TESTS exceptions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. THERMAL POWER not within limit.

B.1 Open reactor trip breakers.

Immediately (continued)

PHYSICS TESTS Exceptions - MODE 2 3.1.10 Watts Bar - Unit 2 3.1-20 Amendment 36, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop average temperature not within limit.

C.1 Restore RCS lowest loop average temperature to within limit.

15 minutes D. Required Action and associated Completion Time of Condition C not met.

D.1 Be in MODE 3.

15 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.10.1 Perform a CHANNEL OPERATIONAL TEST on power range and intermediate range channels per SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1-1.

Prior to initiation of PHYSICS TESTS SR 3.1.10.2 Verify the RCS lowest loop average temperature is 541°F.

In accordance with the Surveillance Frequency Control Program SR 3.1.10.3 Verify THERMAL POWER is 5% RTP.

In accordance with the Surveillance Frequency Control Program SR 3.1.10.4 Verify SDM is within the limits specified in the COLR.

In accordance with the Surveillance Frequency Control Program

FQ (Z) 3.2.1 Watts Bar - Unit 2 3.2-3 Amendment 49, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. FQW (Z) not within limits.

B.1.1 Implement a RAOC operating space specified in the COLR that restores FQW(Z) to within limits.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND B.1.2 Perform SR 3.2.1.1 and SR 3.2.1.2 if control rod motion is required to comply with the new operating space.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR B.2.1

NOTE--------------

Required Action B.2.4 shall be completed whenever Required Action B2.1 is performed prior to increasing THERMAL POWER above the limit of Required Action B.2.1.

Limit THERMAL POWER to less than RATED THERMAL POWER and reduce AFD limits as specified in the COLR.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after each FQW(Z) determination B.2.2 AND Reduce Power Range Neutron Flux 0 High trip setpoints 1% for each 1% that THERMAL POWER is limited below RATED THERMAL POWER by Required Action B.2.1.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQW(Z) determination (continued)

FQ (Z) 3.2.1 Watts Bar - Unit 2 3.2-4 Amendment 49, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

B.2.3 Reduce Overpower T trip setpoints 1% for each 1% that THERMAL POWER is limited below RATED THERMAL POWER by Required Action B.2.1.

AND B.2.4 Perform SR 3.2.31.1 and SR 3.2.1.2.

C. Required Action and Associated Completion Time not met.

C.1 Be in MODE 2.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQW(Z) determination Prior to increasing THERMAL power above the limit of Required Action B.2.1.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

AFD 3.2.3 Watts Bar - Unit 2 3.2-8 Amendment 36, 76 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.

NOTE--------------------------------------------

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY:

MODE 1 with THERMAL POWER 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits.

A.1 Reduce THERMAL POWER to < 50% RTP.

30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore channel.

In accordance with the Surveillance Frequency Control Program

QPTR 3.2.4 Watts Bar - Unit 2 3.2-9 Amendment 76 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be 1.02.

APPLICABILITY:

MODE 1 with THERMAL POWER 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit.

A.1 Reduce THERMAL POWER 3% from RTP for each 1% of QPTR

> 1.00.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each QPTR determination AND A.2 Determine QPTR.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3 Perform SR 3.2.1.1 and SR 3.2.2.1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1.

AND Once per 7 days thereafter AND A.4 Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition.

Prior to increasing THERMAL POWER above the limit of Required Action A.1 AND (continued)

QPTR 3.2.4 Watts Bar - Unit 2 3.2-10 Amendment 76 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.5

NOTES------------

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required Action A.6 shall be completed whenever Required Action A.5 is performed.

Normalize excore detectors to restore QPTR to within limit.

Prior to increasing THERMAL POWER above the limit of Required Action A.1.

AND A.6

NOTE-------------

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1 and SR 3.2.2.1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions at RTP not to exeed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1.

B. Required Action and associated Completion Time not met.

B.1 Reduce THERMAL POWER to 50% RTP.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

QPTR 3.2.4 Watts Bar - Unit 2 3.2-11 Amendment 21, 36, 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1

NOTES----------------------------

1.

With input from one power range neutron flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channels can be used for calculating QPTR.

2.

SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation.

In accordance with the Surveillance Frequency Control Program SR 3.2.4.2

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input to QPTR from one or more power range neutron flux channels are inoperable with THERMAL POWER 75% RTP.

Verify QPTR is within limit using the PDMS.

In accordance with the Surveillance Frequency Control Program

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-1 Amendment 76 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more required channels or trains inoperable.

A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s) or train(s).

Immediately B. One Manual Reactor Trip channel inoperable.

B.1 Restore channel to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR B.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-2 Amendment 21, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train inoperable.

C.1 Restore channel or train to OPERABLE status.

OR C.2.1 Initiate action to fully insert all rods.

AND C.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 48 hours 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months D. One Power Range Neutron Flux-High channel inoperable.

NOTES------------------

1. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

2. Perform SR 3.2.4.2 if input to QPTR from on or more Power Range Neutron Flux channels are inoperable with THERMAL POWER 75% RTP.

D.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-3 Amendment 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F. One Intermediate Range Neutron Flux channel inoperable.

F.1 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR F.2 Increase THERMAL POWER to > P-10.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months G. Two Intermediate Range Neutron Flux channels inoperable.

G.1 Suspend operations involving positive reactivity additions.

Immediately AND G.2 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months H. DELETED I.

One Source Range Neutron Flux channel inoperable.

I.1 Suspend operations involving positive reactivity additions.

Immediately (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-4 Amendment 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J.

Two Source Range Neutron Flux channels inoperable.

J.1 Open reactor trip breakers (RTBs).

Immediately K. One Source Range Neutron Flux channel inoperable.

K.1 Restore channel to OPERABLE status.

OR K.2.1 Initiate action to fully insert all rods.

AND K.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 48 hours 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months L.

Required Source Range Neutron Flux channel inoperable.

L.1 Suspend operations involving positive reactivity additions.

Immediately AND L.2 Close unborated water source isolation valves.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND L.3 Perform SR 3.1.1.1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-7 Amendment 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One RTB train inoperable.

NOTE-----------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE.

Q.1 Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR Q.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months R. One or more channels inoperable.

R.1 Verify interlock is in required state for existing unit conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR R.2 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S. One or more channels inoperable.

S.1 Verify interlock is in required state for existing unit conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR S.2 Be in MODE 2.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-8 Amendment 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One trip mechanism inoperable for one RTB.

T.1 Restore inoperable trip mechanism to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR T.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months U. One Steam Generator Water Level - Low-Low channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

U.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND U.1.2 For the affected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR U.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-10 Amendment 36, 76 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Y. One, two or three Turbine Stop Valve Closure channels inoperable.

Y.1 Place channel(s) in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR Y.2 Reduce THERMAL POWER to < P-9.

76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2

NOTES----------------------------

1.

Adjust NIS channel if absolute difference is > 2%.

2.

Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance calculation to Nuclear Instrumentation System (NIS) channel output.

In accordance with the Surveillance Frequency Control Program (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-15 Amendment 76 Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 1.

Manual Reactor Trip 1, 2 2

B SR 3.3.1.13 NA NA 3 (a), 4 (a), 5 (a) 2 C

SR 3.3.1.13 NA NA 2.

Power Range Neutron Flux a.

High 1, 2 4

D SR 3.3.1.1 111.4% RTP 109% RTP SR 3.3.1.2 SR 3.3.1.7 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15 b.

Low 1 (d), 2 4

E SR 3.3.1.1 27.4% RTP 25% RTP SR 3.3.1.7 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15 3.

Power Range Neutron Flux Rate a.

High Positive Rate 1, 2 4

E SR 3.3.1.7 (b)(c) 6.3% RTP with time constant 2 sec 5% RTP with time constant 2 sec SR 3.3.1.11 (b)(c) b.

High Negative Rate - DELETED 4.

Intermediate Range Neutron Flux 1 (d), 2 (e) 2 F, G SR 3.3.1.1 40% RTP 25% RTP SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c)

(continued)

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(d) Below the P-10 (Power Range Neutron Flux) interlocks.

(e) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-16 Amendment 76 Table 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 5.

Source Range Neutron Flux 2 (f) 2 I, J SR 3.3.1.1 1.33 E5 cps 1.0 E5 cps SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c) 3 (a), 4 (a), 5 (a) 2 J, K SR 3.3.1.1 1.33 E5 cps 1.0 E5 cps SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15 3 (g), 4 (g), 5 (g) 1 L

SR 3.3.1.1 N/A N/A SR 3.3.1.11 (b)(c) 6.

Overtemperature T 1, 2 4

W SR 3.3.1.1 Refer to Note 1 (Page 3.3-21)

Refer to Note 1 (Page 3.3-21)

SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 7.

Overpower T 1, 2 4

W SR 3.3.1.1 Refer to Note 2 (Page 3.3-22)

Refer to Note 2 (Page 3.3-22)

SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 8.

Pressurizer Pressure a.

Low 1 (h) 4 X

SR 3.3.1.1 1964.8 psig 1970 psig SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 b.

High 1, 2 4

W SR 3.3.1.1 2390.2 psig 2385 psig SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 (continued)

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(g) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-20 Amendment 76 Table 3.3.1-1 (page 6 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT 17.

Reactor Trip Breakers (j) (RTBs) 1, 2 2 trains Q

SR 3.3.1.4 NA NA 3 (a), 4 (a), 5 (a) 2 trains C

SR 3.3.1.4 NA NA 18.

Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms 1, 2 1 each per RTB T

SR 3.3.1.4 NA NA 3 (a), 4 (a), 5 (a) 1 each per RTB C

SR 3.3.1.4 NA NA 19.

Automatic Trip Logic 1, 2 2 trains P

SR 3.3.1.5 NA NA 3 (a), 4 (a), 5 (a) 2 trains C

SR 3.3.1.5 NA NA (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(j) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-21 Amendment 76 Table 3.3.1-1 (page 7 of 9)

Reactor Trip System Instrumentation Note 1: Overtemperature T The Overtemperature T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.2% of T span.

T 1 s 1 sTKK 1 s 1 sT TKP PfI Where:

T is measured RCS T, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T is the indicated Tavg at RTP, *.

P is the measured pressurizer pressure, psig P is the nominal RCS operating pressure,

psig K1

K2 */°F 3

K

= */psig 1

sec 2

sec 4

sec 5

sec f1(I)

= *{* + (qt - qb)}

when qt - qb < *% RTP 0% of RTP when *% RTP qt - qb *% RTP

{(qt - qb) - * }

when qt - qb > *% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

These values denoted with

are specified in the COLR.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-22 Amendment 76 Table 3.3.1-1 (page 8 of 9)

Reactor Trip System Instrumentation Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.0% of T span.

T 14s 15sT0 K4-K5 3s 13sT-K6T-T-f2I Where:

T is measured RCS T, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T is the indicated Tavg at RTP, *°F.

K4

3

sec K5

/°F for increasing Tavg

/°F for decreasing Tavg 4

sec K6

/°F when T > T

/°F when T T 5

sec f2(I) = *.

These values denoted with

are specified in the COLR.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-29 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One or more channels inoperable.

L.1 Verify interlock is in required state for existing unit condition.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR L.2.1 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND L.2.2 Be in MODE 4.

13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months M. One Steam Generator Water Level - Low-Low channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

M.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND M.1.2 For the affected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2.1 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND M.2.2 Be in MODE 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

Amendment 76

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Watts Bar - Unit 2 3.4-1 Amendment 76 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a.

Pressurizer pressure is greater than or equal to the limit specified in the COLR, b.

RCS average temperature is less than or equal to the limit specified in the COLR, and c.

RCS total flow rate 380,000 gpm (process computer or control board indication) and greater than or equal to the limit specified in the COLR.

APPLICABILITY:

MODE 1.

NOTE--------------------------------------------

Pressurizer pressure limit does not apply during:

a.

THERMAL POWER ramp > 5% RTP per minute; or b.

THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB parameters not within limits.

A.1 Restore RCS DNB parameter(s) to within limit.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Required Action and associated Completion Time not met.

B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Watts Bar - Unit 2 3.4-2 Amendment 36, 76 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to the limit specified in the COLR.

In accordance with the Surveillance Frequency Control Program SR 3.4.1.2 Verify RCS average temperature is less than or equal to the limit specified in the COLR.

In accordance with the Surveillance Frequency Control Program SR 3.4.1.3 Verify RCS total flow rate is 380,000 gpm (process computer or control board indication) and greater than or equal to the limit specified in the COLR.

In accordance with the Surveillance Frequency Control Program SR 3.4.1.4

NOTE------------------------------

Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 90% RTP.

Verify by precision heat balance method that RCS total flow rate is 380,000 gpm and greater than or equal to the limit specified in the COLR.

In accordance with the Surveillance Frequency Control Program

Reporting Requirements 5.9 5.9 Reporting Requirements (continued)

Watts Bar - Unit 2 5.0-30 Amendment 42, 76 5.9.3 Radioactive Effluent Release Report

NOTE-------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I,Section IV.B.1.

5.9.4 Reserved for Future Use 5.9.5 CORE OPERATING LIMITS REPORT (COLR) a.

Core operating limits shall be established prior to the initial and each reload cycle, or prior to any remaining portion of a cycle, and shall be documented in the COLR for the following:

LCO 3.1.1 Shutdown Margin LCO 3.1.4 Moderator Temperature Coefficient LCO 3.1.5 Rod Group Alignment Limits LCO 3.1.6 Shutdown Bank Insertion Limits LCO 3.1.7 Control Bank Insertion Limits LCO 3.2.1 Heat Flux Hot Channel Factor LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor LCO 3.2.3 Axial Flux Difference LCO 3.9.1 Boron Concentration b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. When an initial assumed power level of 102% RTP is specified in a previously approved method, 100.6% RTP may be used only when feedwater flow measurement (used as input for reactor thermal power measurement) is provided by the leading edge flowmeter (LEFM) as described in document number 11 listed below. When feedwater flow measurements from the LEFM are unavailable, the originally approved initial power level of 102% RTP (3411 MWt) shall be used. The approved analytical methods are, specifically those described in the following documents:

Reporting Requirements 5.9 5.9 Reporting Requirements (continued)

Watts Bar - Unit 2 5.0-31 Amendment 49, 50, 76 5.9.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1.

WCAP-9272-P-A, WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY, July 1985 (W Proprietary). (Methodology for Specifications 3.1.1 - Shutdown Margin, 3.1.4 - Moderator Temperature Coefficient, 3.1.5 - Rod Group Alignment Limits, 3.1.6 - Shutdown Bank Insertion Limit, 3.1.7 - Control Bank Insertion Limits, 3.2.1 - Heat Flux Hot Channel Factor, 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3 -

Axial Flux Difference, and 3.9.1 - Boron Concentration).

2.

WCAP-16996-P-A, Revision 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology)," November 2016.

3.

WCAP-10216-P-A, Revision 1A, RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F(Q) SURVEILLANCE TECHNICAL SPECIFICATION, February 1994 (W Proprietary). (Methodology for Specification 3.2.3 - Axial Flux Difference (Relaxed Axial Offset Control).)

4.

WCAP-12610-P-A, VANTAGE + FUEL ASSEMBLY REFERENCE CORE REPORT, April 1995. (W Proprietary). (Methodology for Specification 3.2.1 - Heat Flux Hot Channel Factor).

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 170 AND 76 TO FACILITY OPERATING LICENSE NOS. NPF-90 AND NPF-96 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391

1.0 INTRODUCTION

By letter dated December 13, 2023 (Agencywide Documents Access and Management System Accession No. ML23347A161), the Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC, the Commission) for changes to the Watts Bar Nuclear Plant, Units 1 and 2 (WBN), technical specifications (TSs). The requested changes would revise various WBN TSs in Sections 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by adopting the following Technical Specifications Task Force (TSTF) travelers:

TSTF-5-A, Revision 1, Delete Safety Limit Violation Notification Requirements TSTF-9-A, Revision 1, Relocate Value for Shutdown Margin to COLR [core operating limits report]

TSTF-12-A, Revision 1, Delete LCO [limiting condition for operation] 3.1.9 and 3.1.11 (Physics Tests Exceptions)

TSTF-13-A, Revision 1, Move SR [surveillance requirement] for 300 ppm [parts per million] MTC [moderator temperature coefficient] Measurement to Frequency Note of SR 3.1.4.3 TSTF-14-A, Revision 4, Add an LCO Item and SR to Mode 2 Physics Tests Exceptions to Verify that Thermal Power <= 5% RTP [rated thermal power]

TSTF-109-A, Clarify the QPTR [quadrant power tilt ratio] Surveillances TSTF-110-A, Revision 2, Delete SR Frequencies Based on Inoperable Alarms TSTF-135-A, Revision 3, RPS [reactor protection system] and ESFAS [engineered safety feature actuation system] Instrumentation TSTF-136-A, Combine LCO 3.1.1 and 3.1.2 TSTF-142-A, Increase the Completion Time When the Core Reactivity Balance is Not Within Limit TSTF-241-A, Revision 4, Allow Time for Stabilization After Reducing Power Due to QPTR Out-of-Limit TSTF-256-A, Modify MODE 2 STE [special test exception] Applicability TSTF-339-A, Revision 2, Relocate TS Parameters to COLR The amendments would also delete one-time historical information from TS SRs 3.1.3.1 and 3.1.4.1 and make editorial changes for items that are not consistent with the Standard Technical Specifications (STS).

2.0 REGULATORY EVALUATION

2.1 Requested Changes The proposed changes for each TSTF traveler are described in the relevant section of this safety evaluation.

2.2 Applicable Regulations and Guidance As described in Title 10 of the Code of Federal Regulations (10 CFR) 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The general considerations that guide the Commission include, as stated in 10 CFR 50.40(a), how the TSs provide reasonable assurance that the health and safety of the public will not be endangered. Also, to issue an operating license, of which TSs are a part, the Commission must make the findings of 10 CFR 50.57, Issuance of operating license, including the 10 CFR 50.57(a)(3)(i) finding that there is reasonable assurance that the activities authorized by the operating license can be conducted without endangering the health and safety of the public.

Pursuant to 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of an operating license desires to amend the license, application for an amendment must be filed with the Commission fully describing the changes desired, and following as far as applicable, the form prescribed for original applications. The technical information to be included in an application for an operating license is governed by 10 CFR 50.34(b).

The regulation at 10 CFR 50.36(a)(1) requires each applicant for a license authorizing operation of a utilization facility to include in the application proposed TSs in accordance with the requirements of 10 CFR 50.36, Technical specifications. The regulation at 10 CFR 50.36(a)(1) requires an applicant to submit, as part of the application, a summary statement of the bases or reasons for such specifications, other than those covering administrative controls. However, per 10 CFR 50.36(a)(1), these TS bases shall not become part of the technical specifications.

As required by 10 CFR 50.36(b), the TSs will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to 10 CFR 50.34, Contents of applications; technical information. The Commission may include such additional TSs as the Commission finds appropriate.

The regulation at 10 CFR 50.36(c) requires, in part, that the TSs include items in the following categories: (1) safety limits (SLs), limiting safety systems settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls.

As required by 10 CFR 50.36(c)(2)(i), the TSs will include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Per 10 CFR 50.36(c)(2)(i), when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.

The regulation at 10 CFR 50.36(c)(3), Surveillance requirements, requires TSs to include items in the category of SRs, which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within SLs, and that the LCOs will be met.

The regulation at 10 CFR 50.36(c)(5), Administrative controls, requires administrative controls, which are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

The regulation further requires each licensee to submit any reports to the Commission pursuant to approved TSs as specified in 10 CFR 50.4, Written communications.

The NRC staffs guidance for the review of TSs is in chapter 16, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP), dated March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STS for each of the light-water reactor nuclear designs. NUREG-14311 contains the STS for Westinghouse plants.

Section IV, The Commission Policy, of the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (58 FR 39132), dated July 22, 1993, states, in part:

The purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by identifying those features that are of controlling importance to safety and establishing on them certain conditions of operation which cannot be changed without prior Commission approval.

[T]he Commission will also entertain requests to adopt portions of the improved STS, even if the licensee does not adopt all STS improvements.

The Commission encourages licensees to use the improved STS as the basis for plant-specific [TSs].

[I]t is the Commission intent that the wording and Bases of the improved STS be used to the extent practicable.

Although the NRC-approved TSTF travelers listed in the LAR were based on changes to previous revisions of NUREG-1431, the NRC staffs review of this LAR includes consideration of whether the proposed changes are consistent with Revision 5 of NUREG-1431. Additionally, the NRC staff determined that the TS changes approved in the TSTF travelers in the LAR are applicable to the WBN TSs because the units are a Westinghouse design, and the NRC staff approved the various travelers for Westinghouse designs. Revision 5 of NUREG-1431 provides example TS LCOs and acceptable remedial actions that meet the requirements in 10 CFR 50.36(c)(2) for a standard Westinghouse plant design.

1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21259A155 and ML21259A159, respectively).

3.0 TECHNICAL EVALUATION

3.1 TSTF-5-A, Revision 1, Delete Safety Limit Violation Notification Requirements 3.1.1 Description of TSTF NUREG-1431, Revision 1, contained several requirements to be completed if a SL is violated.

TSTF-5-A, Revision 1 (ML040340460), deletes the notification, reporting, and restart requirements of STS 2.2.3, 2.2.4, 2.2.5, and 2.2.6 if an SL is violated.

3.1.2 Proposed TS Changes As described in LAR section 2.1, the licensee proposed to delete WBN TSs 2.2.3, 2.2.4, 2.2.5, and 2.2.6 from TS 2.2, SL Violations, because they either are duplicative, are contained in other requirements, or are required to comply with regulations such as 10 CFR 50.36.

3.1.3 Staff Evaluation of Proposed TS Changes The NRC staff confirmed that the TSTF traveler is applicable to WBN by reviewing the licensees submittal and comparing it to the approved TSTF traveler. The licensee stated that these proposed changes are identical to the changes in the approved TSTF traveler and are consistent with the STS (NUREG-1431). The NRC staff reviewed the proposed changes and noted that redundant requirements and direction exist for each TS that is proposed to be deleted:

The NRC staff finds that the proposed changes do not adversely impact plant safety, that the violation notification requirements are adequately addressed by a regulation or required program, and that the proposed changes are consistent with the STS and TSTF-5-A, Revision

1. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

Proposed TS to be deleted Redundant Requirement/Direction 2.2.3, Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , notify the NRC Operations Center, in accordance with 10 CFR 50.72.

10 CFR 50.36(c)(7), Initial notification 2.2.4, Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the Plant Manager and Site Vice President.

TVA quality assurance (QA) program 2.2.5, Within 30 days a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the NSRB [Nuclear Safety Review Board],

the Plant Manager, and Site Vice President.

10 CFR 50.36(c)(8), Written Reports 10 CFR 50.73 TVA QA program 2.2.6, Operation of the unit shall not be resumed until authorized by the NRC.

10 CFR 50.36(c)(1), Safety limits, limiting safety system settings, and limiting control settings 3.2 TSTF-9-A, Revision 1, Relocate Value for Shutdown Margin to COLR 3.2.1 Description of TSTF NUREG-1431, Revision 1, contained various Required Actions and SRs that required the licensee to verify that the shutdown margin was greater than or equal to a specified value or within limits. TSTF-9-A, Revision 1 (ML040400130), relocates the specific value for Shutdown Margin (SDM) located throughout the STS to the COLR.

3.2.2 Proposed TS Changes and Variations As described in LAR section 2.2, the licensee proposed to revise WBN TSs 3.1.1, SHUTDOWN MARGIN (SDM) - Tavg > 200oF, and 3.1.10, PHYSICS TESTS Exceptions - MODE 2, to relocate the values for SDM to the COLR. As noted in LAR section 2.2.2, the licensee also proposed several variations to WBN TSs 3.1.5, Rod Group Alignment Limits, 3.1.6, Shutdown Bank Insertion Limits, and 3.1.7, Control Bank Insertion Limits.

3.2.3 Staff Evaluation of Proposed TS Changes and Variations The NRC staff confirmed that the TSTF traveler is applicable to WBN by reviewing the licensees submittal and comparing it to the approved TSTF traveler. NRC Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications (ML031130447), provides guidance to licensees who want to relocate cycle-specific parameters from the TSs to the COLR whose values are determined using an NRC-approved methodology that is referenced in a TS administrative reporting requirements section. WBNs reporting requirements are located in TS 5.9.5, Core Operating Limits Report (COLR).

There are several differences between the affected TSs listed in TSTF-9-A, Revision 1, which are applicable to Westinghouse plants, and the licensees proposed changes. These differences are primarily due to the prior partial adoption of TSTF-9-A by the licensee in Amendment No.

120 (WBN, Unit 1) and Amendment No. 20 (WBN, Unit 2) (ML18079A029). Additionally, with the proposed adoption of TSTF-12-A, Revision 1, TS 3.1.9, PHYSICS TESTS Exceptions - MODE 1, would be deleted in its entirety instead of being modified in accordance with TSTF-9-A. This proposed change is evaluated in section 3.3 of this safety evaluation. Similarly, TS 3.1.2, Shutdown Margin (SDM) - Tavg 200oF, would be deleted with the proposed adoption of TSTF-136-A, as evaluated in section 3.9 of this safety evaluation.

STS 5.6.3a and 5.6.3b include a listing of the individual TSs that address the core operating limits and identify NRC-approved methodologies used for establishing the core operating limits.

Accordingly, the licensee proposed to revise TS 5.9.5a and 5.9.5b to reflect the proposed changes to TS 3.1.1. To maintain consistency with the STS, the licensee also proposed to revise the information listed in TS 5.9.5 to add TSs previously relocated to the COLR into the itemized list. Specifically, in TS 5.9.5a, the licensee proposed to add LCO 3.1.5, which relocated the SDM to the COLR in Amendment Nos. 120 and 20. The licensee also proposed to add LCO 3.1.5 to TS 5.9.5b to associate it with WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology.

Based on the above, the proposed TS changes are consistent with GL 88-16, TSTF-9-A, Revision 1, and the licensees prior-approved partial adoption of TSTF-9-A. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.3 TSTF-12-A, Revision 1, Delete LCO 3.1.9 and 3.1.11 (Physics Tests Exceptions) 3.3.1 Description of TSTF NUREG-1431, Revision 1, contained LCOs 3.1.9, PHYSICS TESTS Exceptions - MODE 1, and 3.1.11, SHUTDOWN MARGIN (SDM) Test Exceptions, and the associated Bases. The physics tests that LCO 3.1.9 required were rod cluster control assembly (RCCA) Pseudo Ejection Test, RCCA Pseudo Drop and Misalignment Test, and Xenon Stability Measurements.

The physics test that LCO 3.1.11 required was Rod Worth Measurement in the N-1 condition.

TSTF-12-A, Revision 1 (ML040340463), deleted STS 3.1.9 and 3.1.11 since the LCO 3.1.9 tests were only contained in initial plant startup testing programs and the LCO 3.1.11 N-1 measurement technique was no longer being used. In addition, TSTF-12-A revised LCO 3.0.7 to reflect the elimination of the subject Test Exception LCOs.

WBN TS 3.1.9 currently allows selected control rods and shutdown rods to be positioned outside their specified alignment limits and insertion limits to conduct PHYSICS TESTS in MODE 1 (Power Operation) to verify certain core physics parameters. As noted in the LAR, WBN TSs do not contain a TS 3.1.11, SDM Test Exceptions.

3.3.2 Proposed TS Changes and Variations As described in LAR section 2.3, the licensee proposed to delete WBN TS 3.1.9 in its entirety, delete the reference to LCO 3.1.9 in WBN, Unit 1, LCO 3.0.7, and replace the reference to LCO 3.1.9 in WBN, Unit 2, LCO 3.0.7 with a reference to LCO 3.1.10. As noted in LAR section 2.3.2, the licensee also proposed several variations to TSTF-12-A for TSs 3.1.9, PHYSICS TESTS Exceptions - MODE 1, 3.1.10, PHYSICS TESTS Exceptions - MODE 2, and 3.1.11, SHUTDOWN MARGIN (SDM) Test Exceptions.

3.3.3 Staff Evaluation of Proposed TS Changes and Variations The physics tests that LCO 3.1.9 required are RCCA Pseudo Ejection Test, RCCA Pseudo Drop and Misalignment Test, and Xenon Stability Measurements. The NRC-approved TSTF traveler determined that the deletion of these tests exceptions is acceptable since these tests are never performed during post-refueling startup testing, and per the traveler, these physics tests were only contained in some initial plant startup testing programs. Further, the NRC staff notes that the licensee stated in its LAR that the subject physics test exception is no longer performed at WBN during post-refueling startup testing. The staff determined that the current format and content of WBN TS 3.1.9 matches that of the STS on which TSTF-12-A was based. Therefore, the NRC staff determined that the adoption of TSTF-12-A is acceptable because the corresponding WBN TSs are consistent with the approved TSTF traveler and the WBN TSs, as modified, would continue to reflect the current plant operating requirements.

Regarding the licensees proposed variations, the NRC staff determined that the differences from the traveler are editorial, administrative, and non-technical and have no effect on the licensees adoption of the traveler; therefore, the variations are acceptable.

Regarding the licensees proposed variation for not adopting the travelers deletion of TS 3.1.11, the NRC staff determined that the WBN units do not specify this TS, so the travelers change is not applicable to the WBN TSs, and the variation has no effect on the licensees adoption of the traveler.

Regarding the licensees proposed inclusion of reference to TS 3.1.10 in the WBN, Unit 2, LCO 3.0.7, the staff finds that the change is consistent with the WBN, Unit 1, LCO 3.0.7. Since both WBN units are similarly designed facilities, the change is acceptable.

The NRC staff determined that TS 3.1.9 can be deleted because these LCO tests are never performed during post-refueling startup testing, and the licensee stated that the tests are no longer being performed at WBN, which is consistent with TSTF-12-A. Therefore, the staff finds the licensees proposed change for the deletion of TS 3.1.9 acceptable. The staff also determined that the proposed variations, as described above, have no effect on the licensees adoption of the traveler. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.4 TSTF-13-A, Revision 1, Move SR For 300 ppm MTC Measurement to Frequency Note of SR 3.1.4.3 3.4.1 Description of TSTF NUREG-1431, Revision 1, contained SRs 3.1.4.2 and 3.1.4.3. SR 3.1.4.2 required verification of MTC measurement at 300 ppm, and SR 3.1.4.3 addressed accelerated frequency requirement if the 300 ppm surveillance limit was not met. TSTF-13-A, Revision 1 (ML040340455), deletes SR 3.1.4.2 and replaces it with a Note in SR 3.1.4.3 since the intent of the SR 3.1.4.2 was to determine the next frequency for SR 3.1.4.3. The traveler determined that the subject change would be consistent with other SRs.

WBN TS SR 3.1.4.2 currently requires verification of the MTC limits once each cycle. A Note in the Frequency column of the SR states, Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm.

WBN TS SR 3.1.4.3 requires verifying if the MTC is within the lower limit at a frequency of once each cycle. The SR specifies two Notes, as follows:

1.

If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.4.3 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

2.

SR 3.1.4.3 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.

3.4.2 Proposed TS Changes and Variations As described in LAR section 2.4, the licensee proposed to delete SR 3.1.4.2, move the SR 3.1.4.2 Note to SR 3.1.4.3 as Note 1, and renumber the Notes accordingly. The licensee also proposed a variation regarding the numbering of the SRs.

3.4.3 Staff Evaluation of Proposed TS Changes and Variations The MTC relates a change in core reactivity to a change in reactor coolant temperature (a positive MTC means that reactivity increases with increasing moderator temperature; conversely, a negative MTC means that reactivity decreases with increasing moderator temperature). The reactor is designed to operate with a negative MTC over the largest possible range of fuel cycle operation. The limitations on MTC are provided to ensure that the value of this coefficient (i.e., beginning of cycle (BOC) and end of cycle (EOC) MTC values) remains within the limiting conditions assumed in the Final Safety Analysis Report (FSAR) accident and transient analyses.

WBN TS SRs 3.1.4.2 and 3.1.4.3 (similar to SRs 3.1.3.1 and 3.1.3.2 in NUREG-1431, Revision

5) verify that the MTC is less negative than the specified value for EOC full-power conditions.

The licensee, consistent with TSTF-13-A, Revision 1, proposed the deletion of SR 3.1.4.2 since the intent of the performance of SR 3.1.4.2 was only to determine the next frequency for SR 3.1.4.3. Identifying this frequency determination as an SR implies that it must be met in order to meet the LCO per SR 3.0.1, which was determined (as stated in TSTF-13-A) to be not true for this limit. SR 3.0.1 states, in part, that SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO.

SR 3.1.4.3 currently contains a Note addressing the accelerated frequency required if the 300 ppm Surveillance limit is not met.

The licensee also proposed that the Note in the Frequency column of SRs 3.1.4.2 and 3.1.4.3 be moved to the Surveillance column of SR 3.1.4.3 for clarification purposes. This change would make the use of this type of Note consistent with other SRs. The proposed change is non-technical in nature and does not affect the manner in which the MTC is verified. No accident precursors or dose consequences are affected by this change.

Based on the above, the NRC staff determined that SR 3.1.4.2 can be deleted since the intent for the performance of SR 3.1.4.2 was only to determine the next frequency for SR 3.1.4.3.

SR 3.1.4.3, as modified by the addition of a Note in the surveillance column, is consistent with other SRs. The NRC staff also determined that the current format and content of the WBN TS SRs 3.1.4.2 and 3.1.4.3 matches that of the STS on which the TSTF-13-A revisions were based (i.e., NUREG-1431, Revision 1). Therefore, the NRC staff finds that the adoption of TSTF-13-A is acceptable because it provides more appropriate SRs to ensure that the necessary quality of systems and components is maintained. The NRC staff also finds the licensees proposed changes to SRs 3.1.4.2 and 3.1.4.3 acceptable. Regarding the licensees proposed variation, the NRC staff determined that the differences from the traveler are editorial, administrative, and non-technical and have no effect on the licensees adoption of the traveler; therefore, the variation is acceptable. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.5 TSTF-14-A, Revision 4, Add an LCO Item and SR to Mode 2 Physics Tests Exceptions to Verify that Thermal Power <= 5% RTP 3.5.1 Description of TSTF NUREG-1431, Revision 1, contained LCO 3.1.10, PHYSICS TESTS Exceptions-Mode 2, which permits relaxations of existing LCOs to allow certain PHYSICS TESTS to be performed.

TSTF-14-A, Revision 4 (ML040340471), adds LCO requirements and an SR to verify that thermal power is within the defined power level for Mode 2 during performance of Physics Tests.

According to the traveler, this is because there was a TS Action that addressed thermal power not within limit; however, there was no corresponding LCO or SR for such condition.

3.5.2 Proposed TS Changes and Variation The licensee proposed changes to WBN LCO 3.1.10 and SR 3.1.10.3, which are described next (additions shown in bolded text, deletions shown is strikeout).

3.5.2.1 Addition of LCO 3.1.10 Note c WBN TS 3.1.10 currently allows a reduction in the number of required channels for LCO 3.3.1, Reactor Trip System (RTS) Instrumentation, Functions 2, 3, 6, and 16.e, provided that the following LCO Notes a and b are met:

a. RCS lowest loop average temperature is 541°F; and

b. SDM is 1.6% k/k.

The proposed change would delete the word and from LCO Note a, add ; and at the end of LCO Note b, and add a new Note c as shown in bold text below:

a. RCS lowest loop average temperature is 541°F; and

b. SDM is 1.6% k/k; and

c. THERMAL POWER is 5% RTP.

3.5.2.2 Addition of SR 3.1.10.3 SR 3.1.10.3 Verify THERMAL POWER is 5% RTP. In accordance with the Surveillance Frequency Control Program 3.5.2.3 Renumbering current SR 3.1.10.3 as SR 3.1.10.4 SR 3.1.10.34 Verify SDM is 1.6% k/k.

3.5.2.4 Proposed Variation The licensee proposed a variation regarding the application of the Surveillance Frequency Control Program (SFCP) to the Frequency of proposed new SR 3.1.10.3, in lieu of the Frequency of 30 minutes provided in the traveler.

3.5.3 Staff Evaluation of Proposed TS Changes and Variation 3.5.3.1 Addition of LCO 3.1.10 Note c The primary purpose of the MODE 2 PHYSICS TESTS exceptions is to permit relaxation of existing LCOs to allow certain PHYSICS TESTS to be performed. This testing is an integral part of the plants design, construction, and operation.

The proposed addition of LCO 3.1.10 Note c would require the licensee to ensure that Thermal Power is < 5% RTP before suspending requirements of specified LCOs and reducing specified RTS instrumentations. Should the thermal power exceed 5% RTP, and consequently the unit enters MODE 1, the modified LCO 3.1.10 APPLICABILITY statement, with the addition of Note c, would prevent exiting the LCO and its required actions. Since the proposed change does not add any new equipment, modify any interfaces with any existing equipment, alter the equipments function, or change the method of operating the equipment, the primary purpose of the LCO stated above would remain unaffected by the change. Further, the proposed change does not alter plant conditions in a manner that could affect other plant components; therefore, the change is acceptable.

3.5.3.2 Addition of SR 3.1.10.3 The licensees proposed change would add SR 3.1.10.3 in accordance with TSTF-14-A, Revision 4. This SR requires verification that Thermal Power is < 5% RTP, which would ensure that the plant is not operating in a condition that could invalidate the safety analyses. The proposed change does not reduce the current SRs, which would assure that the necessary quality of systems and components is maintained, and that facility operation will be within the SLs; therefore, the change is acceptable. Renumbering the current SR 3.1.10.3 as SR 3.1.10.4 is appropriate with the addition of the new SR 3.1.10.3, and is an editorial, administrative, and non-technical change; therefore, it is acceptable.

3.5.3.3 Staff Evaluation of Variation The licensees proposed change includes the application of its SFCP to the Frequency of new SR 3.1.10.3 in lieu of the Frequency of 30 minutes provided by TSTF-14-A, Revision 4. The NRC staffs review of the licensees SFCP determined that the program is consistent with the NRC-approved TSTF-425, which was adopted by WBN, Units 1 and 2, with License Amendment Nos. 132 and 36, respectively (ML20028F733). Therefore, the variation and change to the SR frequency is acceptable.

3.5.3.4 TSTF-14-A Conclusion The NRC staff determined that with the addition of Note c in LCO 3.1.10, the licensee would be required to ensure that Thermal Power is within the specified TS limits. The staff also determined that with the addition of SR 3.1.10.3, the licensee would be required to verify that Thermal Power is < 5% RTP to ensure that the plant is not operating in a condition that could invalidate the safety analyses. The staff also determined that the variation, as described above, does not affect the licensees adoption of the traveler. Therefore, the NRC staff finds that the licensees adoption of TSTF-14-A is acceptable because the licensee provides appropriate Actions and SR requirements for a condition when Thermal Power is not within the limits. Based on the above, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.6 TSTF-109-A, Clarify the QPTR Surveillances 3.6.1 Description of TSTF NUREG-1431, Revision 1, contained LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR). The QPTR ensures that the gross radial power distribution remains consistent with the design values used in the safety analyses. In order to clarify the QPTR surveillances, TSTF-109-A (ML040480053) revises certain Required Actions and SRs associated with LCO 3.2.4.

3.6.2 Proposed TS Changes and Variations The licensee proposed the following changes to SRs 3.2.4.1 and 3.2.4.2 (additions shown in bolded text, deletions shown is strikeout):

Proposed change to TS Required Action A.2:

Perform SR 3.2.4.1 Determine QPTR and reduce THERMAL POWER 3% from RTP for each 1% of QPTR > 1.00.

Proposed change to TS SR 3.2.4.1, Note 2:

SR 3.2.4.2 may be performed in lieu of this Surveillance if adequate power range neutron flux channel inputs are not OPERABLE.

Proposed change to TS SR 3.2.4.2, Note:

Only Not required to be performed if until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input to QPTR from one or more power range neutron flux channels are inoperable when THERMAL POWER is 75% RTP.

Proposed change to TS SR 3.2.4.2, Frequency:

Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND In accordance with the Surveillance Frequency Control Program.

The licensee noted a variation regarding the proposed change to SR 3.2.4.2. Specifically, because the frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is subsumed by the SFCP, the frequency and logical connector are proposed to be deleted, as noted above. The licensee also proposed a variation regarding the use of the power distribution monitoring system, which is in use at WBN, Units 1 and 2, in lieu of incore detectors.

3.6.3 Staff Evaluation of Proposed TS Changes and Variations 3.6.3.1 Evaluation of the proposed change to TS Required Action A.2 LCO 3.2.4, Required Action A.2, is intended to result in a periodic re-check and re-adjustment of thermal power based on existing QPTR. Required Action A.2 specifically requires the performance of SR 3.2.4.1, which verifies that the QPTR, as indicated by the Nuclear Instrumentation System (NIS) excore channels, is within its limits. However, the performance of SR 3.2.4.1 may not be viable if NIS excore channel(s) are inoperable. To specify the intended Required Action A.2 more correctly, the licensees proposed change would revise the Action to require Determine QPTR rather than specifying a need for the performance of an SR; therefore, the change is acceptable.

3.6.3.2 Evaluation of the proposed change to TS SR 3.2.4.1, Note 2 SR 3.2.4.1 specifies two Notes. Note 1 allows QPTR to be calculated with three power range channels if THERMAL POWER is 75% RTP and the input from one power range neutron flux channel is inoperable. Note 2 allows the performance of SR 3.2.4.2 in lieu of SR 3.2.4.1 if adequate power range neutron flux channel inputs are not OPERABLE. The TSTF determined that the requirement was overly restrictive and ambiguous as to what adequate... inputs are.

Since the performance of SR 3.2.4.2 in lieu of SR 3.2.4.1 would adequately verify the QPTR 1.02 in all cases, not just when flux channels are inoperable, the modified Note 2 in SR 3.2.4.1 is appropriate. Therefore, the change is acceptable.

3.6.3.3 Evaluation of the proposed changes to TS SR 3.2.4.2, Note and Frequency The TSTF-109 traveler modifies the SR 3.2.4.2 Note to state that the SR is not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the input from one or more power range neutron flux channels are inoperable and the THERMAL POWER is > 75% RTP. With an NIS power range channel inoperable, tilt monitoring for a portion of the reactor core becomes degraded. Large tilts are likely detected with the remaining channels, but the capability to detect small power tilts in some quadrants is decreased. Therefore, the change is acceptable. As explained below under Evaluation of the Variations, the NRC staff finds the licensees proposed change for performing SR 3.2.4.2 in accordance with its SFCP acceptable.

3.6.3.4 Evaluation of the Variations Regarding the proposed variation in SR 3.2.4.2, the NRC staffs review of the licensees SFCP determined that the program is consistent with the NRC-approved TSTF-425, which was adopted by the WBN, Units 1 and 2, with License Amendment Nos. 132 and 36, respectively (ML20028F733). These amendments approved the relocation of SR 3.2.4.2 to the licensees SFCP. Therefore, the variation and change to the SR frequency is acceptable.

Regarding the proposed variation between the licensees plant-specific justification and the TSTF-109-A traveler justification regarding the performance of SR 3.2.4.2 using incore detectors, the NRC staff reviewed the licensees explanation in 3.6.2 of this SE and the related TS requirements. The staff finds that the licensees adoption of TSTF-109-A is not affected by the subject variation; therefore, the variation is acceptable.

3.6.3.5 TSTF-109-A Conclusion The NRC staff determined that LCO 3.2.4, as modified by the revised Required Action A.2 and SR 3.2.4.2, would assure that the TS-specified QPTR limit remains consistent with the design values used in the safety analyses. Further, the staff determined that the proposed variations do not affect the licensees adoption of the traveler. Therefore, the NRC staff finds that the proposed changes to the TSs, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.7 TSTF-110-A, Revision 2, Delete SR Frequencies Based on Inoperable Alarms 3.7.1 Description of TSTF NUREG-1431, Revision 1, contained TS 3.1.5, Rod Group Alignment Limits, TS 3.1.7, Control Bank Insertion Limits, TS 3.2.3, Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology), and TS 3.2.4, Quadrant Power Tilt Ratio (QPTR). TSTF-110-A, Revision 2 (ML20198K276), relocates certain SR frequencies related to specific inoperable alarms from the specified TSs to the plant administrative documents since the alarms themselves do not directly relate to the LCO limits.

3.7.2 Proposed TS Changes The licensee proposed the following changes (additions shown in bolded text, deletions shown is strikeout):

TS 3.1.5, Rod Group Alignment Limits, SR 3.1.5.1 states:

Verify position of individual rods within alignment limit in accordance with the Surveillance Frequency Control Program AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod position deviation monitor is inoperable TS 3.1.7, Control Bank Insertion Limits, SR 3.1.7.2 states:

Verify each control bank insertion is within the limits specified in the COLR in accordance with the Surveillance Frequency Control Program AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod insertion limit monitor is inoperable TS 3.2.3, AXIAL FLUX DIFFERENCE (AFD), SR 3.2.3.1 states:

Verify AFD within limits for each OPERABLE excore channel in accordance with the Surveillance Frequency Control Program AND Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months thereafter with the AFD monitor alarm inoperable TS 3.2.4, QUADRANT POWER TILT RATIO (QPTR), SR 3.2.4.1 states:

Verify QPTR is within limit by calculation in accordance with the Surveillance Frequency Control Program AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter with the QPTR alarm inoperable The licensee also proposed changes to the WBN TS SR 3.1.5.1 Bases. However, the NRC staff did not evaluate the proposed changes to the TS Bases because the Bases are not part of the TSs in accordance with 10 CFR 50.36(a)(1).

3.7.3 Staff Evaluation of Proposed TS Changes 3.7.3.1 Assessment for Deletion of TS Rod Group Alignment Limits (RIL) Monitor in SR 3.1.5.1 The OPERABILITY, including position indication, (i.e., trippable) of the shutdown and control rods is an initial assumption in the safety analyses that assumes rod insertion upon reactor trip.

Maximum rod misalignment is an initial assumption in the safety analysis that directly affects core power distributions and assumptions of available SDM. Rod position indication is required to assess operability and misalignment.

Mechanical or electrical failures may cause a control rod to become inoperable or misaligned from its group. Control rod inoperability or misalignment may cause increased power peaking due to the asymmetric reactivity distribution and a reduction in the total available rod worth for reactor shutdown. Therefore, control rod alignment and OPERABILITY are related to core operation in design power peaking limits and the core design requirement of a minimum SDM.

Limits on control rod alignment have been established, and all rod positions are monitored and controlled during power operation to ensure that the power distribution and reactivity limits defined by the design power peaking and SDM limits are preserved.

The licensees proposed change to SR 3.1.5.1 (i.e., to remove requirements for surveillances when the rod position deviation monitor is inoperable) is identical to that contained in TSTF-110-A, Revision 2. The rod position monitor/alarm is provided as an aid to alert the operator if any rod deviates from the bank position by more than +/- 12 steps. This SR verifies that each control bank insertion is within the limits specified in the COLR.

One of the requirements of the COLR specified in TS 5.9.5 is that:

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

The NRC staff determined that the performance of the SR per the licensees COLR program ensures that the plant is operating within the limits established in its accident analysis. As a result, actions based on the availability of the rod position monitor are not required to be retained in the TSs; therefore, the proposed change is acceptable.

3.7.3.2 Assessment for Deletion of TS Rod Insertion Limit (RIL) Monitor in SR 3.1.7.2 The insertion limits of the shutdown and control rods are initial assumptions in all safety analyses that assume rod insertion upon reactor trip. The insertion limits directly affect core power and fuel burnup distributions, assumptions of available SDM, and initial reactivity insertion rate. TS limits on control rod insertion have been established, and all rod positions are monitored and controlled during power operation to ensure that the power distribution and reactivity limits defined by the design power peaking and SDM limits are preserved. WBN SRs 3.1.5.1 through 3.1.5.3 rely solely upon the Bank Demand Position Indication and the Digital Rod Position Indication (DRPI) systems. The RIL monitor is not used in satisfying these SRs.

The RIL monitor/alarm alerts the operator if the control banks are outside of the insertion limits.

It performs no protective functions assumed in a safety analysis. Considering that rod motion is limited and infrequent during steady-state power operations, verifying that banks are within the limits in accordance with the WBN SFCP allows the operator to detect a bank that is approaching the insertion limits. This specified frequency considers other rod position information that is continuously available to the operator in the control room so that during actual rod motion, deviations can be immediately detected.

Since the rod position indication systems provide accurate information on rod positions, the operators routinely verify rod positions are within limits, and the RIL monitor serves no protective function, the NRC staff has determined that removing the SR when the RIL is inoperable is acceptable.

3.7.3.3 Assessment for Deletion of TS Axial Flux Difference Monitor in SR 3.2.3.1 The axial flux difference (AFD) is a measure of the axial power distribution skewing to either the top or bottom half of the core. The AFD is sensitive to many core-related parameters such as control bank positions, core power level, axial burnup, axial xenon distribution, and to a lesser extent, reactor coolant temperature and boron concentration. The allowed range of the AFD is used in the nuclear design process to confirm that operation within these limits produces core peaking factors and axial power distributions that meet safety analysis requirements.

TS limits on AFD were established in order to ensure that core peaking factors are consistent with the assumptions used in the safety analysis. WBN TSs address these requirements, which require that the indicated AFD be maintained within the target band specified in the COLR, and that the AFD is verified to be within limits on a routine basis using the operable excore channels.

Additionally, there is an AFD monitor/alarm, which does not perform any protective functions, to aid the operator in maintaining AFD within limits. This monitor/alarm is not relied upon for these surveillances. However, there are TS requirements to perform the AFD verifications more frequently during periods when this monitor is not operable.

The licensee proposed to revise SR 3.2.3.1 to remove SR frequency changes related to the operability of the AFD monitor alarm and to revise the associated Bases to remove the discussion of the alarm operation.

The NRC staff determined that the AFD monitor alarm is provided as an operators aid for maintaining AFD within established limits and that it performs no protective functions assumed in a safety analysis. Although AFD indication ensures that core peaking factors do not exceed assumptions in the accident analysis, the NRC staff determined that removal of the SR when the AFD monitor alarm is inoperable is acceptable since the excore detectors (for which no change is proposed) are capable of verifying the AFD. Therefore, the NRC staff finds that the removal of the AFD monitor alarm requirement in SR 3.2.3.1 is acceptable.

3.7.3.4 Assessment for Deletion of TS Quadrant Power Tilt Ratio Monitor in SR 3.2.4.1 The QPTR is a measure of the radial power distribution within the core. The QPTR limit ensures that the gross radial power distribution remains consistent with the design values used in the safety analysis. The power density at any point in the core must be limited to maintain the fuel design criteria. Together, WBN TS 3.2.3, TS 3.2.4, and TS 3.1.7 provide limits on process variables that characterize and control the three-dimensional power distribution of the reactor core. Control of these variables ensures that the core operates within the fuel design criteria and that power distribution remains within the bounds used in the safety analysis.

Precise radial power distribution measurements are made during startup testing, after refueling, and periodically during power operation. The TS limit on QPTR is addressed by an LCO and SRs, which require that the QPTR be maintained within its limit and verified on a routine basis using the excore detectors. Additionally, there is a QPTR monitor/alarm, which does not perform any protective functions, to aid the operator in maintaining QPTR within the TS limit. Although this monitor/alarm is not relied upon for the TS-required QPTR SRs, there are TS requirements to perform the QPTR verification more frequently during periods when this monitor is not operable.

The licensee proposed to revise SR 3.2.4.1 to remove requirements associated with the QPTR monitor alarm and to revise the associated Bases to remove the discussion of alarm operability.

Specifically, the SR would be modified to remove the requirement to calculate QPTR and verify that it is within limits when the QPTR alarm is inoperable. The TS requirements to maintain QPTR less than or equal to 1.02 when reactor power is greater than 50 percent RTP, and the associated action statements would be unchanged.

The NRC staff determined that the QPTR monitor alarm is provided as an operators aid for maintaining QPTR within established limits and that it performs no protective functions assumed in a safety analysis. When the QPTR exceeds its limit, it does not necessarily mean a safety concern exists. The proposed change would remove requirements associated with the QPTR monitor alarm, but would leave the TS QPTR limit and QPTR SRs unchanged. Per 10 CFR 50.36(c)(3), SRs assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.

SR 3.2.4.1 verifies that the QPTR, as indicated by the NIS excore channels, is within its limits.

The surveillance frequency for SR 3.2.4.1 is controlled under the SFCP. Valid inputs to the detector current comparator from the upper and lower sections from three or four power range channels are required for the QPTR alarm to be OPERABLE. The licensees proposed change to the SR 3.2.4.1 frequency does not change this requirement. For those causes of QPTR that occur quickly (e.g., a dropped rod), there typically are other indications of abnormality that prompt a verification of core power tilt. Therefore, the NRC staff finds that the removal of the QPTR monitor alarm requirement in SR 3.2.4.1 is acceptable.

In addition to the above assessments, the NRC staff also determined that the current format and content of the WBN TSs listed above matches that of the STS on which TSTF-110-A was based (i.e., NUREG-1431, Revision 1). Therefore, the NRC staff finds that the adoption of the TSTF-110-A is acceptable because, as discussed above, the requirements for the specified alarms do not directly relate to the LCO limits.

3.7.3.5 TSTF-110-A Conclusion The NRC staff determined that SRs frequencies related to the specific alarms listed above could be removed from the TSs since the requirements for those alarms do not directly relate to the LCO limits. Further, the alarms do not perform any protective functions assumed in a safety analysis. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.8 TSTF-135-A, Revision 3, RPS and ESFAS Instrumentation 3.8.1 Description of TSTF TSTF-135-A, Revision 3 (ML040500736), makes several improvements to TS 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to enhance consistency with standard Improved TS presentation, thereby improving usability.

TSTF-135-A, Revision 3, predominately:

(1) Changes functions with an Applicability of With RTBs closed and Rod Control System capable of rod withdrawal to state With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. Similarly, the related Required Actions (C.2 and K.2) are revised to exit this Applicability in lieu of opening RTBs.

(2) Simplifies and clarifies actions associated with inoperability of:

a. intermediate rage neutron flux detectors

b. source range neutron flux detectors

c. reactor trip system interlocks

d. one reactor trip mechanism 3.8.2 Proposed TS Changes and Variations As described in the LAR, the licensee proposed changes to TS 3.3.1 and TS 3.3.2 consistent with TSTF-135-A, Revision 3.

The licensee proposed variations to the changes of TSTF-135-A, Revision 3, to the extent that they are not applicable. For example, the licensee did not propose to delete WBN TS 3.3.1, Condition L, or the Table 3.3.1-1 information associated with it because STS 3.3.9 is not applicable to WBN. The licensee also proposed changes in lettering since the WBN TSs do not have the same lettering as the STS.

3.8.3 Staff Evaluation of Proposed TS Changes and Variations The NRC staff confirmed that TSTF-135-A is applicable to WBN. The licensee identified and justified proposed variations. The staff evaluated the proposed changes and proposed variations to the TSs and determined that the proposed changes are consistent with the TSTF traveler and that the variations, which are administrative in nature, are consistent with the intent of the traveler. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.9 TSTF-136-A, Combine LCO 3.1.1 and 3.1.2 3.9.1 Description of TSTF NUREG-1431, Revision 1, contained two Shutdown Margin LCOs. LCO 3.1.1 applied to RCS temperatures above 200oF and LCO 3.1.2 applied to RCS temperatures 200oF. The ACTIONS tables of the two LCOs were identical. TSTF-9-A moves Shutdown Margin requirements to the COLR. With the TSTF-9-A changes implemented in TS 3.1.1 and 3.1.2, there were no effective differences between the two LCOs. TSTF-136-A (ML040500749) combines the requirements of LCO 3.1.2 into LCO 3.1.1, deletes TS 3.1.2, and makes associated renumbering changes to account for the deletion of LCO 3.1.2.

3.9.2 Proposed TS Changes and Variation The licensee proposed combining the LCO 3.1.1 and LCO 3.1.2 requirements without renumbering all of the TS sections after TS 3.1.2. The licensee cited the choice to not renumber the TS sections after TS 3.1.2 as a variation. The licensee proposed retaining the TS numbering after TS 3.1.2 as-is and designating TS 3.1.2 as Deleted.

3.9.3 Staff Evaluation of Proposed TS Changes and Variation The NRC staff notes that the adoption of the TSTF-9-A changes discussed in section 3.2 of this SE is necessary to allow the combination of the requirements in LCOs 3.1.1 and 3.1.2. Given the acceptability of the TSTF-9-A changes, the staff confirmed that TSTF-136-A is applicable because WBN is a Westinghouse plant and the current format and content of TS 3.1.1 and 3.1.2 match that of NUREG-1431, Revision 1. The staff evaluated the proposed changes to the TSs and determined that the proposed changes are consistent with the TSTF traveler and appropriate for the WBN plant design. Regarding the licensees proposed variation, the staff determined that the differences from the traveler are editorial, administrative, and non-technical and have no effect on the licensees adoption of the traveler. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.10 TSTF-142-A, Increase the Completion Time When the Core Reactivity Balance is Not Within Limit 3.10.1 Description of TSTF NUREG-1431, Revision 1, specified a Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the Required Actions when the measured core reactivity is not within limit. TSTF-142-A (ML040490204) revises TS 3.1.3, Core Reactivity, Condition A, Measured core reactivity not within limit, to extend the Completion Time for Required Actions A.1 and A.2 to 7 days.

3.10.2 Proposed TS Changes The licensee proposed to change the completion time of TS 3.1.3, Condition A, Required Action A.1, Re-evaluate core design and safety analysis, and determine that the reactor core is acceptable for continued operation, and Required Action A.2, Establish appropriate operating restrictions and SRs, from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 7 days.

3.10.3 Staff Evaluation of Proposed TS Changes The NRC staff confirmed that TSTF-142-A is applicable to WBN by reviewing the licensees submittal and comparing it to the TSTF traveler. The licensee stated that these proposed changes are identical to the changes in the traveler. The actions require a reevaluation of the core design and safety analysis to determine if the reactor core is acceptable for continued operation within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Further, the existing TSs require the establishment of appropriate operating restrictions and SRs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Predicted versus measured reactivity anomaly evaluation is a complex task requiring data collection and transmittal, coordination across several organizations, some of which could be external to the licensee, and the development and implementation of appropriate controls and SRs based on the cycle-specific operating data.

Experience has shown that the time allowed by existing TS requirements may not be reasonable to complete this complex task. The proposed 7-day completion times provide sufficient time to analyze the cycle-specific operating data and develop and implement appropriate controls.

The proposed TS change is consistent with TSTF-142-A and is acceptable because of the conservatisms used in designing the reactor core and performing the safety analyses, and the low probability of a design-basis accident or anticipated transient approaching the core-design limits during the 7-day period. Based on this, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.11 TSTF-241-A, Revision 4, Allow Time for Stabilization After Reducing Power Due to QPTR Out-of-Limit 3.11.1 Description of TSTF NUREG-1431, Revision 1, TS 3.2.4, Quadrant Power Tilt Ratio (QPTR), Required Actions A.1 and A.2 require that Thermal Power be reduced if QPTR is out of limits. Action A.3 requires that the peaking factors be verified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and once per 7 days thereafter. LCO 3.2.1A and B also require a power reduction if FQ(Z) is not within limit. TSTF-241-A, Revision 4 (ML040611034), provides more appropriate Required Actions and Completion Times when the QPTR LCO is not met. It revises the Completion Times of Required Actions in STS 3.2.1 by adding the phrase after each FQ(Z) determination to the end of the Completion Times for Required Actions A.1, A.2, A.3, and A.4 in STS 3.2.1A and after each FQC(Z) determination to the end of the Completion Times for Required Actions A.1, A.2, and A.3 in STS 3.2.1B.

TSTF-241-A also revises the Required Actions and Completion Times of Required Actions A.1, A.2, A.3, A.5, and A.6 in STS 3.2.4. The Completion Time for STS 3.2.4, Required Action A.1, is changed from 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each QPTR determination. STS 3.2.4, Required Action A.2, is changed from Perform SR 3.2.4.1 and reduce THERMAL POWER 3% from RTP for each 1% of QPTR > 1.00, to Perform SR 3.2.4.1. The first Completion Time for STS 3.2.4, Required Action A.3, is changed from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1. STS 3.2.4, Required Action A.5, is revised to add a new Note stating, Required Action A.6 shall be completed if Required Action A.5 is performed. STS 3.2.4, Required Action A.5, is also revised by changing the Required Action from Calibrate excore detectors to show QPTR of 1.0 to Normalize excore detectors to restore QPTR to within limit. The Completion Time for STS 3.2.4, Required Action A.6, is changed from Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching RTP or Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1 to Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1.

3.11.2 Proposed TS Changes and Variations The licensee proposed revising the Required Actions and Completion Times of Required Actions A.1, A.2, A.3, A.5, and A.6 in TS 3.2.4, in accordance with TSTF-241-A. The licensee also proposed taking a technical variation to TSTF-241 by adding after each FQW(Z) determination to the end of the Completion Times for Required Actions B.2.1, B.2.3, and B.2.3 in TS 3.2.1.

3.11.3 Staff Evaluation of Proposed TS Changes and Variations The NRC staffs evaluation of the licensees plant-specific adoption of TSTF-241-A, along with variations, is below in sections 3.11.3.1 and 3.11.3.2, respectively.

3.11.3.1 TSTF-241-A related changes TSTF-241-A revises the Required Actions and Completion Times of Required Actions A.1, A.2, A.3, A.5, and A.6 in STS 3.2.4. The NRC staff reviewed the proposed changes to WBN TS 3.2.4 related to TSTF-241-A. The staff determined that the current format and content of TS 3.2.4 matches that of the STS that the TSTF-241-A revisions were based on (i.e., NUREG-1431, Revision 1). Therefore, the NRC staff determined that the adoption of the TSTF-241 related changes is acceptable because they are more appropriate Required Actions and Completion Times when the QPTR LCO is not met.

3.11.3.2 Variations Regarding STS 3.2.1, TSTF-241-A revises the Completion Times of Required Actions by adding the phrase after each FQC(Z) determination to the end of the Completion Times for Required Actions A.1, A.2, and A.3 in STS 3.2.1B. The licensee stated that these changes had previously been adopted for Required Actions A.1, A.2, and A.3.

In LAR section 2.11.4, the licensee provided justification for the technical variation to TSTF-241-A. The NRC staff reviewed the justification and notes that while changes to Completion Times for TS 3.2.1, Required Actions B.2.1, B.2.2, and B2.3, are not part of the TSTF-241-A changes, they are an extension of the reasoning behind the approval of TSTF-241. Namely, the Completion Times will require that the corrective actions be repeated after each subsequent FQW(Z) measurement that is not within limit. The staff notes that extending the TSTF-241-A changes to Required Actions B.2.1, B.2.2, and B.2.3 is not an adoption of a TSTF traveler, per se. TSTF-241-A was a part of evolutionary changes to the STS that were incorporated into Revision 4 of NUREG-1431. Nonetheless, the NRC staff finds that extending the TSTF-241-A changes to Required Actions B.2.1, B.2.2, and B.2.3 is acceptable because it clarifies when remedial measures are required and makes the presentation of Required Actions B.2.1, B.2.2, and B.2.3 consistent with Required Actions A.1 through A.3.

3.11.3.3 TSTF-241-A Conclusion The NRC staff confirmed that TSTF-241-A is applicable to WBN. The licensee identified proposed variations. The staff evaluated the proposed changes to the TSs and determined that the changes are consistent with the TSTF traveler and appropriate for the WBN plant design.

Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.12 TSTF-256-A, Modify MODE 2 STE Applicability 3.12.1 Description of TSTF NUREG-1431, Revision 1, contained an LCO, PHYSICS TESTS Exceptions - MODE 2, with an APPLICABILITY statement phrased as MODE 2 during PHYSICS TESTS. If THERMAL POWER increased above 5%, Required Action A.1 calls for immediately opening the control rod drive trip breakers. However, with the Applicability as written, the unit would be in MODE 1 and the LCO and its requirements would no longer apply. TSTF-256-A (ML040610943) revises the APPLICABILITY statement in STS 3.1.10 from MODE 2 during PHYSICS TESTS, to During PHYSICS TESTS initiated in MODE 2. The change to the Applicability ensured that Required Action A.1 would be completed if THERMAL POWER exceeded 5% RTP.

3.12.2 Proposed TS Changes The licensee proposed changing the APPLICABILITY statement in TS 3.1.10 from MODE 2 during PHYSICS TESTS, to During PHYSICS TESTS initiated in MODE 2.

3.12.3 Staff Evaluation of Proposed TS Changes The NRC staff confirmed that TSTF-256-A is applicable to WBN because it is a Westinghouse plant with TSs that contain an LCO, PHYSICS TESTS Exceptions - MODE 2, with an APPLICABILITY statement phrased as MODE 2 during PHYSICS TESTS. The licensee did not identify any proposed variations. The staff evaluated the proposed changes to the TSs and determined that the proposed changes are consistent with the TSTF traveler and appropriate for the WBN plant design because they would rephrase the APPLICABILITY statement to match that in the traveler. The staff determined that the revised Applicability will ensure that Required Action B.1 would be completed if THERMAL POWER exceeded 5% RTP. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.13 TSTF-339-A, Revision 2, Relocate TS Parameters to COLR 3.13.1 Description of TSTF TSTF-339-A, Revision 2 (ML003723269), relocates certain TS parameters to the COLR consistent with WCAP-14483, Generic Methodology for Expanded Core Operating Limits Report (ML020430092).

3.13.2 Proposed TS Changes and Variations The licensee proposed that TS Figure 2.1.1-1, referenced in TS 2.1.1, Reactor Core SLs, which would be replaced by TS 2.1.1.1 for departure from nucleate boiling ratio (DNBR) and TS 2.1.1.2 for peak fuel centerline temperature, be relocated to the COLR. The licensee also proposed related changes to TS Table 3.3.1-1, Reactor Trip System Instrumentation, for overtemperature T and overpower T and in TS 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits. Finally, the licensee proposed non-technical variations due to differences in nomenclature and an apparent error in the traveler.

3.13.3 Staff Evaluation of Proposed TS Changes and Variations The NRC staff confirmed that TSTF-339-A, Revision 2, is applicable to WBN by reviewing the licensees submittal and comparing it to the TSTF traveler. The licensee stated that the proposed changes have non-technical variations to the changes in the traveler, including slight variations in site-specific nomenclature.

The limits on the parameters that are removed from the TSs and added to the COLR must be developed and justified using NRC-approved methodologies. All accident analyses performed in accordance with these methodologies must meet the applicable NRC-approved limits of the safety analysis. The removal of parameter limits from the TSs and their addition to the COLR does not obviate the requirement to operate within these limits. Any changes to the limits must be performed in accordance with WBN TS 5.9.5.c. If any of the applicable limits of the safety analysis are not met, prior NRC approval of the change is required.

The NRC staff approved WCAP-14483 as an acceptable method to relocate certain TS requirements to the COLR consistent with GL 88-16. TSTF-339-A incorporated these TS changes into the Westinghouse STS (ML12100A222) and was later revised to TSTF-339-A, Revision 2, to incorporate changes based on plant-specific submissions. The NRC staff reviewed sections 4.4.1 and 4.4.2 of the WBN Dual-Unit Updated Final Safety Analysis Report (ML23312A225) and compared them to the proposed DNBR and peak fuel centerline temperature in the TS update and determined that the changes are consistent with the WBN licensing basis.

The NRC staff finds that the proposed relocation of the affected TS parameters to the COLR is in accordance with the guidance of the GL 88-16 and that the changes described above are consistent with TSTF-339-A, Revision 2, and the guidance provided in WCAP-14483-A.

Regarding the licensees proposed variations, the staff determined that the differences from the traveler are editorial, administrative, and non-technical and have no effect on the licensees adoption of the traveler. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

3.14 Additional Proposed TS Changes The licensee proposed other changes that are not related to the adoption of TSTF travelers.

The licensee described the changes as either the removal of information that is no longer relevant or editorial changes to promote consistency with format and content guidance and to promote internal consistency.

3.14.1 Description of Additional Proposed TS Changes The licensee proposed the following additional TS changes:

1. Delete the phrase initial fuel loading and from the frequency of SR 3.1.3.1 and SR 3.1.4.1.

2. Add s to limit in TS 3.1.1 Condition A and Required Action A.1.

3. Delete Once from SR 3.1.4.1 Frequency.

4. Shift the indentation of ACTIONS (continued) to the left on Unit 1, page 3.1-10.

5. Add insertion to SR 3.1.7.2.

6. Change EXCEPTIONS to Exceptions in the header and add a space before and after the dash in the title of TS 3.1.10 on Unit 1, TS page 3.1-23.

7. Delete quotation marks from reduced to 3 required channels... in LCO 3.1.10.

8. Relocate (continued) above the horizontal line on Unit 1, pages 3.2-1 and 3.2-2.

9. Delete thereafter from the Required Action A.2 Completion Time of TS 3.2.4.

10. Change the SR 3.2.4.1 Note designations from a. and b. to 1. and 2., respectively, on Unit 2, page 3.2-11

11. Change the subscript in TS and TM to lower case on Unit 1, pages 3.3-8 and 3.3-9.

3.14.2 Staff Evaluation of Additional Proposed TS Changes The licensee provided background information and justification for the proposed additional TS changes. The NRC staff reviewed the justifications. The staff finds that change 1 is acceptable because it removes historical information that is no longer relevant and does not affect TS usage or implementation. The staff finds that changes 2 through 11 are acceptable because they are editorial and promote consistency both internal to the WBN, Units 1 and 2, TSs as well as with TS guidance in NUREG-1431. The staff also finds that the editorial changes do not affect TS usage or implementation. Therefore, the NRC staff finds that the proposed changes, as described in the LAR, are acceptable because the TSs, as modified, will continue to meet 10 CFR 50.36.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendments on September 27, 2024. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or change SRs. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission previously issued a proposed finding that the amendments involve no significant hazards consideration published in the Federal Register on February 20, 2024 (89 FR 12876),

and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: R. Grover, NRR M. Hamm, NRR J. Ambrosini, NRR S. Sun, NRR N. Carte, NRR Date: December 17, 2024

ML24285A207 NRR-058 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NAME TSierra KGreen ABaxter DATE 10/11/2024 10/25/2024 10/29/2024 OFFICE NRR/DSS/SNSB/BC NRR/DSS/STSB/BC NRR/DEX/EICB/BC NAME PSahd SMehta FSacko DATE 07/30/2024 09/16/2024 10/31/2024 OFFICE OGC - NLO NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME JWachutka DWrona KGreen DATE 11/21/2024 12/17/2024 12/17/2024

v t e Letter Sequence Other
EPID:L-2023-LLA-0172, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) (Open)
Initiation Request Acceptance Administration Questions Answers Results Approval... Other: ML24285A207, ML24354A158
MONTHYEAR2024-01-16 [Table View]

ML24285A207

Text

SUBJECT:

Dear Delson Erb:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

Navigation menu

Search