Text

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Conversion to Improved Standard TSs
	ML20133B585
Person / Time
Site:	Byron, Braidwood
Issue date:	12/13/1996
From:	Graesser K, Stanley G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20133B589	List: ML20133B585;
References
	NUDOCS 9701060043
	Download: ML20133B585 (104)
	v • d • e

,

Comnumwr.lth Edium Company

' firaidwtxxl Generating Station

z/ Route el, Ikix 8 t

'Isracrville, IL GHOFXil9 TclHI5-4542801

,Y '

December 13,1996 United States Nuclear Regulatory Commission Attention:' Document Control Desk Washington, D.C. 20555-0001

Subject:

Application for Amendment to Appendix A, Technical Specifications, for Facility Operating Licenses:

Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 .

,e e

A Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licer,ses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457 Conversion to the Improved Standard Technical Specifications

References:

1. Karl L. Kaup and Kenneth L. Graesser (Comed) letter to NRC Document Control Desk, " Notification ofIntent to Adopt the Improved Standard Technical Specifications," dated May 31,1995.

2. NUREG-1431, " Standard Technical Specifications - Westinghouse Plants," Revision 1, dated April 1995.

Ladies and Gentlemen:

Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.90),

Commonwealth Edison Company (Comed) proposes to amend Appendix A, Technical Specifications, for Facility Operating Licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Nuclear Power Station, Units I and 2 (Byron), and Braidwood Nuclear Power Station, Units I and 2 (Br- ood), respectively.

N j'~% ,

C# ~~9701060043 961213 \ y ADOCK 05000454 gt\

PDR p PDR

/

( h)1{a% '

q A Unicom Company Q

I~ l r

n- NRC Document Control Desk December 13,1996

' k)

Reference 2). The proposed license amendment request to convert the Byron and Braidwood CTS to the Byron and Braidwood improved Technical Specifications (ITS) is enclosed with this letter.

The proposed license amendment request was prepared considering the guidance of Nuclear Energy Institute (NEI) NEI 96-06, " improved Technical Specifications Conversion Guidance,"

dated August 1996. NEl 96-06 was issued after the start of the ITS project. The detailed description and justification of this proposed license amendment request consists of seventeen (17) volumes. A detailed description of the contents and organization of the 17 volumes is included in Attachments I through 7 of this letter, and are described below:

Attachment I," Synopsis of the Proposed License Amendment Request," describes the organization and content of the submittal.

Attachment 2, " Differences between Byron and Braidwood," lists the Technical Specification differences between Byron and Braidwood. This attachment is provided to facilitate NRC review.

Attachment 3, " Existing and Future License Amendment Requests to be incorporated into the ITS," provides a listing of all currently docketed license amendment requests that have been incorporated into this license amendment request. The currently docketed license amendment request regarding boraflex has not been incorporated into this license amendment request pending p final resolution of the issue. Additionally, a license amendment request to implement the V Pressure / Temperature Limits Report (PTLR) will be made in the near future and is required to support this license amendment request.

Attachment 4, "Pending and Proposed ISTS Change Travelers," provides a listing of the pending and proposed changes to the ISTS incorporated into this license amendment request.

Attachment 5, "'Beyond Scope' Changes," provides a listing of those changes that are difTerent than both CTS and ISTS.

Attachment 6, '"Beyond Scope Bracketed' Changes," provides a listing of those changes to CTS parameters beyond those needed to conform with the ITS.

Attachment 7, " CTS Requirements Relocated to Other Licensee Controlled Documents," provides a listing of the CTS requirements relocated to licensee controlled documents, the proposed location of the relocated item, and the change control mechanism that will be applied to the relocated item.

Implementation of the Byron and Braidwood ITS will require the performance of a number of new surveillance requirements. Comed intends to treat these new requirements as being " met" at the time of implementation, with the first performance of these new surveillance requirements scheduled to be completed within the required frequency from the date ofimplementation.

g N

NRC Document Control Desk December 13,1996 n

5 4 V

Any revisions to the Byron and Braidwood Updated Final Safety Analysis Report (UFSAR) required as a result of this proposed license amendment request will be made in accordance with 10 CFR 50.71(e).

Currently, Comed intends to implement this proposed license amendment request at both Byron and Braidwood in November 1997. This date is based on the time required for procedure revisions, including the development of new programs, training schedules for both licensed and non licensed operators, and the timing ofimplementation with respect to current outage schedules.

This date is also predicated on the NRC review being completed and a Safety Evaluation issued by July 1997. However, the implementation date at Byron is tentative and dependent upon fmal determination of the steam generator replacement outage schedule.

The proposed changes in this license amendment request have been reviewed and approved by both On-site and Off-site Review in accordance with Comed procedures. Comed has reviewed this proposed license amendment request in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists. An environmental assessment has been completed and is included in Attachment 8.

Comed is notifying the State of Illinois of our application for this license amendment request by transmitting a copy of this letter and its attachments to the designated State Official.

(']

v To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects these statements are not based on my personal knowledge, but on information furnished by other Comed employees, contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.

Comed requests a meeting at your earliest convenience to discuss a review schedule and contents of this license amendment request. Please address any comments or questions regarding this matter to Mr. Harold D. Pontious, Jr., Braidwood Nuclear Licensing Administrator, at (630) 663-7205.

Very truly yours, Very truly yours, e n Ken Graesser Site Vice President Site Vice President Braidwood Nuclear Power Station Byron Nuclear Power Station O 1

~

l

1 l

NRC Document Control Desk December 13,1996 g

L)

Signed before me Signed before me on this lM day on this / 8 day af M nL htA . .._._.:JW::::::::

o(, hts;=lm,_1R96____,_____'

! OFFICIAL SEAL !,; OFFICIAL SEdtl

!{ TINA M TAMAYO SANTOUN

, notAny Pustic. STATE ol INOIS l ll JACQUELINE T EVANS!! '

' NoTAMy pygtge, gIATi of ILLieggHg by( Nj %, y_y coqgy<9_n Emn!$of

.a;mT'D9XfilIT'JDDWrC by - _yffl W omssmNEw'Maung:smbl

Maade, cad w

~

Notary Public/

/ Nutary Public -

Attachments (8)

Enclosure (1) cc. A. B. Beach, Regional Administrator - Rlli C.1. Grimes, Chief, Technical Specifications Branch - NRR G. F. Dick Jr., Byron Project Manager - NRR

\ R. R. Assa, Braidwood Project Manager - NRR S. D. Burgess, Senior Resident inspector - Byron C. J. Phillips, Senior Resident inspector - Braidwood Office of Nuclear Facility Safety - IDNS t'%

'd ..

r l

O I

l l

ATTACHMENT 1 l SYN 0PSIS OF THE

O PROPOSED LICENSE AMENDMENT REQUEST 4

i l

J i

l I

i lO ,

i L.'

Attachment 1 g

V SYNOPSIS OF THE IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL (page 1 of 5)

The submittal for the conversion to Improved Technical Specifications (ITS) consists of 17 volumes and related attachments to the transmittal letter. The 17 volumes consist of the a) plication of NRC Selection Criteria (Split Report) and ITS Section packages. 3elow is a brief description of the contents of the Split Re) ort and each of the Section packages, as well as a brief explanation of how tie material was prepared and the designations utilized.

APPLICATION OF NRC SELECTION CRITERIA The Selection Criteria provides a discussion of how the 10 CFR 50.36(c)(2)(ii) criteria were applied to the Byron and Braidwood Current Technical Specifications (CTS) requirements. Also included i a matrix which cross references the following documents: 1) CTS: . 2) NUREG--0452. " Standard Technical Specifications for Westinghouse Pressurized Water Reactors."

Revision 4: 3) proposed ITS. where applicable; and 4) 10 CFR 50.36(c)(2)(ii) criteria for inclusion of requirements. For those CTS requirements that do not meet any of the NRC selection criteria and are not retained in the proposed ITS. an evaluation of the CTS requirement against the criteria is g provided in Appendix A (WCAP-11618 Evaluated) and Appendix B (Non WCAP-11618).

SECTION PACKAGES FOR SECTIONS 1.0 THROUGH 5.0 (14 SECTIONS)

Each of the Section packages corresponds to a Section of the proposed ITS.

contains the required information to review the ITS Section and is organized as described below:

1 TAB 1 Byron ITS ;

Contains the proposed Byron ITS LCOs and Bases.

TAB 2 Braidwood ITS Contains the proposed Braidwood ITS LCOs and Bases. !

1

(

U 1

u _

Attachment 1 AJ SYNOPSIS OF THE IMPROVED TECHNICAL SPECIFICATIONS SUBMITTkL (page 2 of 5)

TAB 3 Byror CTS Markuos. and TAB 4 Braicwood CTS Markuos Contains annotated copies of the CTS pages which show the' disposition of existing requirements into the pro)osed ITS. The pages are arranged in CTS order. The upper rig 1t hand corner of the CTS page is annotated with all the ITS Section numbers in which the CTS page occurs. Items on the CTS page that are addressed in other proposed ITS sections are annotated with the appropriate location.

Where a proposed ITS requirement differs from a CTS requirement.

individual details of the CTS revision are annotated with alpha-numeric designators which relate to the appropriate Discussion of Change (DOC). The DOC provides a concise justification for the change. The DOCS are located behind the fifth Tab (labeled CTS DOCS) of each Section package. The alpha-numeric designators also relate to the evaluations supporting a finding of No Significant Hazards Consideration (NSHC) located behind the tenth Tab (labeled NSHC) of .

each Section package.

The DOCS are numbered sequentiall within each letter category for each ITS Section. The proposed c anges for each CTS requirement are separated into the following categories: l Desianator Cateacry l A ADMINISTRATIVE - changes to the CTS that result in no additional or reduced restrictions or flexibility. These changes are supported in aggregate by a single NSHC.

R RELOCATIONS - changes to the CTS that 1 encompass the requirements that do not meet the l selection criteria of 10 CFR 50.36(c)(2)(ii).

These changes are supported in aggregate by a l single NSHC. l M MORE RESTRICTIVE - changes to the CTS that result in added restrictions or reduced l flexibility. These changes are supported in l aggregated by a single NSHC.

O l

Attachment 1 SYNOPSIS OF THE IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL (page 3 of 5)

TAB 3 3vron CTS Markuos. and TAB 4 3raidwood CTS Markupji (continued)

Desianator Cateaory LA LESS RESTRICTIVE " Generic" - changes to the .

CTS that eliminate detail and relocate the detail to a licensee controlled document.

Typically, this involves details of system design and function, or procedural detail on methods of conducting a surveillance. These :

changes are supported in aggregate by a single NSHC.

L LESS RESTRICTIVE " Specific" - changes to the CTS that result in reduced restrictions or added flexibility. Each less restrictive change is supported by a corresponding evaluation supporting a finding of NSHC.

The CTS Bases pages are replaced in their entirety. An "A" DOC justifies the replacement.

The CTS pages in the Section packages reflect License Amendments issued as of December 13. 1996, and License Amendment Renests described in Attachment 4 to the submittal letter.

TAB 5 CTS DOCS Contains the DOCS which describe each proposed change to the CTS.

TAB 6 LCO Markuos Contains annotated co)ies of the applicable NUREG-1431. Revision 1.

LCOs which show how tie proposed ITS LCO differs from the NUREG LCO.

Where a proposed ITS LC0 requirement differs from the NUREG LCO, individual details of the change are annotated with alpha-numeric designators which relate to the appropriate Justification for Difference (JFD). The JFD provides a concise justification for the change. The LCO JFDs are located behind the seventh Tab (labeled LCO JFDs) of each Section package.

O

1 l

l Attachment 1 m

U SYNOPSIS OF THE IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL (page 4 of 5)

TAB 6 Lc0 Markuos (continued) ,

The LCO JFDs are numbered sequentially within each letter category ,

for each ITS Section. The differences are separated into the l following categories. l Desianatqt Cateaory B BRACKETED CHANGES - changes which reflect plant specific information where the NUREG contains brackets.

C GENERIC CHANGES - changes which reflect generic modifications to NUREG-1431. Revision 1.

These changes have either been ap3 roved by the NRC or have been pro)osed by the 4RC or industry. Generic clanges that were proposed as of October 2, 1996, either as TSTFs or WOG ,

travelers are addressed. Attachment 2 to the i submittal letter provides a summary of the j generic change disposition.

P PLANT SPECIFIC CHANGES - changes which reflect plant specific requirements and information.

TAB 7 LC0 JFDs Contains the JFDs which describe the differences from the NUREG-1431 LCOs.

TAB 8 Bases Markuos Contains annotated copies of the applicable NUREG-1431. Revision 1, Bases which show how the proposed ITS Bases differs from the NUREG Bases. Where a proposed ITS Bases requirement differs from the NUREG

Bases. individual details of the change are annotated with alpha-numeric designators which relate to the ap3ropriate JFD. The JFD provides a concise justification for the clange. The Bases JFDs are located behind the ninth Tab (labeled Bases JFDs) of each Section package.

O

h Attachment 1 SYNOPSIS OF THE IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL (page 5 of 5)

TAB 8 Bases Markuos (continued)

The Bases JFDs are numbered sequentially within each letter category for each ITS Section. The differences are separated into the following categories.

Desianator Cateaory B BRACKETED CHANGES - changes which reflect plant specific information where the NUREG contains brackets.

C GENERIC CHANGES - changes which reflect generic modifications to NUREG-1431. Revision 1.

These changes have either been ap] roved by the NRC or have been pro)osed by the 4RC or industry. Generic clanges that were proposed as of October 2, 1996, either as TSTFs or WOG travelers are addressed. Attachment 2 to the r submittal letter provides a summary of the :

generic change disposition.

P PLANT SPECIFIC CHANGES - changes which reflect plant specific requirements and information.

l TAB 9 Bases JFDs Contains the JFDs which describe the differences from the NUREG-1431 '

Bases.

TAB 10 NSliC l Contains the evaluations required by 10 CFR 50.91(a) supporting a finding of No Significant Hazard Consideration (NSHC). Generic j evaluations for a finding of NSHC have been written for each category :

of changes except Category "L." The evaluations supporting a finding !

of NSHC are ordered as follows: A. R. M. LA, and L. Each evaluation i is annotated to correspond to the DOC addressed in the NSHC. ;

)

Additionally, information in support of the conclusion that this i amendment request satisfies the categorical exclusion specified in 10 CFR 51.22(c) to perform an Environmental Assessment or !

(7 Environmental Impact Statement is provided as Attachment 8 to the l V submittal letter, j

)

I

.. -_. - .- - . .. - . -- .... -- .- - - ~_ - _ - _ - . .- -

O ;

l l

1 l

-l u

ATTACHMENT 2

DIFFERENCES BETWEEN

O 4

BYRON AND BRAIDWOOD l

4 l

1 i

i i-i ,

p ,

4 i

I i :

' l i i lo 4 l s'

a w..-m , m.. - -

c 3 . . - w, ,.,.-...-.--,,-....-,-..-e--..,---, - - - - . . - . . . , , - - - - < . - - . . . - - . . - - , - - - - , - . . - -

l p .

n

\

l Attachment 2 i

DIFFERENCES BETWEEN BYRON AND BRAIDWOOD (page 1 of 4)

ITS SECTION CTS LCO ITS LCO AND BASES DESCRIPTION OF DIFFERENCE (Applicable DOC) (Applicable JFD) 1.0 USE AND APPLICATION None None 2.0 SAFETY LIMITS SL 2.1.1. Footnotes Not applicable Deleted expired cycle specific reactor core safety (DOC A ) limits for each station.

3.0 LCO AND SR None None APPLICABILITY 3.1 REACTIVITY CONTROL None None SYSTEMS 3.2 POWER DISTRIBUTION None None LIMITS 3.3 INSTRUMENTATION Table 2.2-1. Footnotes Not applicable Deleted expired Byron cycle specific values.

(DOC A,)

Table 3.3-4 (DOC A,) Not Applicable Deleted expired Braidwood cycle specific values.

Table 3.3-4 (DOC LA3 ) Bases 3.3.5 The degraded voltage instrumentation allowable values are different for each station.

None Bases 3.3.5 The undervoltage and dagraded voltage instrumentation design descriptions are modified to reflect station design d fferences.

3.4 REACTOR COOLANT Not applicable Bases 3.4.1 Byron Unit 2. required minimum Reactor Coolant SYSTEM System flow rate is met with a 92% indicated flow rate rather than the 2 95% indicated flow rate for Byron Unit I and Braidwood Units 1 and 2.

3.5 EMERGENCY CORE LC0 3.5.1 (DOC A3 ) Not applicable Deleted expired cycle specific baron concentration COOLING SYSTEMS values for each station.

LCO 3.5.5 (DOC A;,) Not applicable Deleted expired cycle specific boron concentration values for each station.

3.6 CONTAINMENT SYSTEMS None None

m ,m J Y Attachment 2 DIFFERENCES BETWEEN BYRON AND BRAIDWOOD (page 2 of 4)

ITS SECTION CTS LCO ITS LCO AND BASES DESCRIFTION OF DIFFERENCE (Applicable DOC) (Applicable JFD) 3.7 PLANT SYSTEMS SR 4.7.1.1 Not applicable Deleted expired Braidwood cycle specific condition (DOC A3 ) of operation.

Not applicable Bases SR 3.7.1 Braidwood does not test the Main Steam Safety Valves (JFD P3 and P ) to the OM-1987 code. Byron IST program references ANSI /ASME OM-1-1987 and applicable addenda.

LCO 3.7.5 LC0 3.7.9. Bases 3.7.9 Braidwood ultimate heat sink design consists of a (Various DOCS) (Various JFDs) cooling pond. The Byron ultimate heat sink design consists of mechanical draft cooling towers.

SR 4.7.6.e.3 Not applicable Deleted expired Braidwood cycle specific SR 4.7.6.e.5 surveillance requirements.

(DOC A22 )

LC0 3.7.7 Not applicable Deleted expired Braidwood time specific (DOC Am ) Specification exception.

SR 4.7.7.d.3 SR 3.7.12.4 Braidwood confims the ability of the Nonaccessible (DOC L27 ) Area Exhaust Filter Plenum Ventilation System (two trains) to maintain the ECCS equipment rooms at a negative pressure while operating at a specified flow rate through the train and per bank. Byron perfoms this test while operating at a specified flow rate through the train only.

SR 4.7.7.d.3 SR 3.7.12.4 The specified nonaccessible Area Exhaust Filter (DOC A .) Bases SR 3.7.12.4 Plenum Ventilation System test flow rates are different for each station.

SR 4.9.4.2 Not applicable Deleted expired Braidwood time specific surveillance (DOC A3 ) , requirement exception.

(. b,a V d Attachment 2 DIFFERENCES BETWEEN BYRON AND BRAIDWOOD (page 3 of 4)

ITS SECTION CTS LCO ITS LCO AND BASES DESCRIPTION OF DIFFERENCE (Applicable DOC) (Applicable JFD) 3.8 ELECTRICAL POWER LCO 3.8.2.1. LC0 3.8.4. LC0 3.8.5 The battery types are different for each station.

SYSTEMS LC0 3.8.2.2 Bases 3.8.4. Bases 3.8.5 Byron uses Gould batteries and Braidwood uses AT&T (DCC uA and Au ) batteries.

LCO 3.8.2.1 LC0 3.8.4. LC0 3.8.5 The battery crosstie load limit is different for LC0 3.8.2.2 (JFD P and P3 ) each station. The battery crosstic load limit for BasesS.8.4. Bases 3.8.5 Byron is 63 amps and for Braidwood the limit is 100 amps.

SR 4.8.2.1.2.a SR 3.8.4.1 Based on different battery types. the specified battery teminal voltages are different for each station. The specified battery teminal voltage for Byron is 126 volts and for Braidwood the voltage is 130.5 volts.

SR 4.8.2.1.2.d SR 3.8.4.3. SR 3.8.4.4 The battery capacity tests are different for each SR 4.8.2.1.2.e Bases SR 3.8.4.3 station. Byron uses O performance discharge test Bases SR 3.8.4.4 and Braidwood uses a modified performance discharge test.

Table 4.8-2 SR 3.8.6.6. SR 3.8.6.7 Float voltage and specific gravity parameters are Bases SR 3.8.6.6 different for each station.

Bases SR 3.8.6.7 LCO 3.8.3.1 LC0 3.8.9. LCO 3.8.10 The listing of Distribution System buses are LC0 3.8.3.2 Bases 3.8.9 different for each station. Details in the Bases have been revised to reference two primary 480 V ESF buses at Byron and only one primary 480 V ESF bus at Braidwood 3.9 REFUELING None None OPERATIONS 4.0 DESIGN FEATURES 4.1.1 (DOC A2 ) 4.0 The site descriptions for each station are

, different.

,m

,.m b

Attachment 2 DIFFERENCES BETWEEN BYRON AND BRAIDWOOD (page 4 of 4)

ITS SECTION CTS LCO ITS LCO AND BASES DESCRIPTION OF DIFFERENCE (Applicable DOC) (Applicable JFD) 5.0 ADMINISTRATIVE 6.9.1.4 (DOC A,) Not applicable Deleted expired Byron time specific reporting CONTROLS requirement.

6.9.1 (DOC A3 ) Not applicable Revised a Byron reference from " unit" to " facility" consistent with other CTS sections.

4.0.5.b (DOC LAg ) Not applicable Relocated Byron specific requirements associated with ASME Section XI testing requirements.

SR 4.4.5.2. SR 4.4.5.4 Spec 5.5.9.b. Spec 5.5.9.e The references to unit specific cycles associated SR 4.4.5.5.d Spec 5.6.9.d with the steam generator inspection requirements are different for each station.

SR 4.7.6. SR 4.7.7 Spec 5.5.11 The specified train and bank flow rates for the (DOC yA and L3 ) Nonaccessible Area Exhaust Filter Plenum Ventilation System test and the specified wattage range for the Control Room Ventilation Filtration System heaters are different in the Ventilation Filter Testing Program each station.

O ATTACHMENT 3 EXISTING AND FUTURE O LICENSE AMENDMENT REQUESTS TO BE INCORPORATED INTO THE ITS O

n fm n Attachment 3 EXISTING AND FUTURE LICENSE AMENDMENT REQUEST TO BE INCORPORATED INTO THE ITS (page 1 of 2)

LICENSE AMENDMENT REQUEST AFFECTED ITS AFFECTEO CTS ASSOCIATED (Letter Title, Letter Date, Abbreviated Subject) LCOfSPECIFICATION PAGE(s) DOC {s) AND JFD(s)

Application for Amendment to Facility Operating Licenses: Specification 5.5.9 3/4 4-14 5.0 - A,, I

Steam Generators." dated August 19. 1996. Specification 5.6.9 3/4 4-16 3/4 4-17 (Steam Generator 3.0 volt criteria) 3/4 4-17a 3/4 4-17b 3/4 4-17c 3/4 4-17d Application for Amendment to Facility Operating Licenses: LC0 3.7.12 3/4 7-17 (Braidwood) 3.7 - A.,

"Non-Accessible Area Exhaust Filter Plenum Ventilation 3/4 7-19 (Byron)

System.' dated August 23. 1996.

(Nonaccessible Area Exhaust Filter Plenum Ventilation System)

Application for Amendment to Facility Operating Definitions 1-4 1.0 - A3 Licenses-Reactivity Controls Systems. dated December 21. 1995:

and LC0 3.1.4 3/4 1-14 Additional Infonnation Regarding the Removal of Cycle-Specific LC0 3.1.5 3.1 - A' 3 3/4 1-15 Parameter Limits from Technical Specifications. dated October LC0 3.1.6 3/4 1-20

24. 1996. 3/4 1-21 (Core Operating Limits Report)

LCO 3.2.1 3/4 2-1 3.2 - A, LC0 3.2.2 3/4 2-2 LC0 3.2.3 3/4 2-3 3/4 2-4 -

3/4 2-5 3/4 2-8 6-22 Specification 5.6.5 5.0 - A ,

Application for Amendment to Appendix A. Technical None 3/4 6-8 5.0 - A3 Specifications. for Facility Operating Licenses: " Containment Vessel Structural Integrity." dated November 4. 1996 (Tendon Grease Removal).

,-- p , .

b Attachment 3 EXISTING AND FUTURE LICENSE AMENDMENT REQUEST TO BE INCORPORATED INTO THE ITS (page 2 of 2)

LICENSE AMENDMENT REQUEST AFFECTED ITS AFFECTED CTS ASSOCIATED (Letter Title, Letter Date, Abbreviated Subject) LCOISPECIFICATION PAGE(s) DOC (s) AND JFD(s)

Application for Amendment to Appendix. Technical LCO 3.7.1 3/4 7-1 3.7 - A3 Specifications. for Facility Operating Licenses: Main Steam 3/4 7-2 Safety Valves Technical Specification Change Request, dated 3/4 7-3 April 29. 1996.

(MSSV's)

Application for Amendment to Appendix A. Technical LC0 3.7.14 3/4 9-13 3.7 - A Specifications 3.9.11. " Water Level-Storage Pool". 5.6.1.1. LC0 3.7.15 3.7-P;3(LCOs)

" Criticality." 6.9.1.10. " Criticality Analysis of Byron and LCO 3.7.16 3.7 - P3(Bases)

Braidwood Station Fuel Storage Racks." dated November 5. 1996 Specification 4.3.1 5-5 4.0 - A.

(Boraflex), 4.0 - P, None 6-23 5.0 - A 3 Reactor Coolant System (RCS) Pressure and Temperature Limits 5.6.6 None None Report (PTLR)

(PTLR)'

1. As described in the associated Discussion of Changes (DOCS) and Justifications for Differences (JFDs). the ITS conversion does not include Specifications which may be impacted by the final resolution of the boraflex issue. A future request will provide these specifications.

2. The initial PTLR will be provided for review and approval at a future date. Upon NRC review the dates which are blank in Specification 5.6.6 will be provided.

O ATTACHMENT 4 PENDING AND PROPOSED lO ISTS CHANGE TRAVELERS 1

i' l

) '.

4 i

}

i l'

a l-lO I

4 1

_ _ . . - _ . . __._ _ a

i O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 1 of 11)

W TU S Cs ST S EXPLANATION OF INCORPORATION STATUS f

EDITORIAL (1)

TSTF-1 R1 Pending 3.0.5 F NA C3 C3 TSTF-2 R1 Pending 3.8.3 F NA C3 C3 TSTF-3 R1 Rejected 1.1 NI Not incorporated based on being rejected. -- --

3.4.16 NI Not incorporated based on being rejected. -- --

3.7.18 NI Not incorporated based on being rejected. -- --

TSTF-4 R1 Pending 1.1 P Did not incorporate LTOP arming temperature in the PTLR C3/P3 --

definition and added PORV lift settings to 5.6.6.

5.6.6 P Did not incorporate LTOP arming temperature in the PTLR C, --

definition and added PORV lift settings to 5.6.6.

TSTF-5 R1 Approved 2.0 FE Editorial change made in B 2.1.1 to be consistent with B Cr C3 2.1.2 change.

TSTF-6 R1 Approved 3.0.1 F N/A C3 --

TSTF-7 R1 Withdrawn 3.0.3 NI Not incorporated based on being withdrawn. -- --

TSTF-8 R1 Pending 3.8.1 P Plant specific change makes changes to SR 3.5.1.12 and C, C,/Py SR 3.5.1.13 not necessary.

B 3.0.1 F N/A --

C, TSTF-9 R1 Approved 3.1 FE Editorial change made to be consistent with the wording of C, C, other LCOs & Bases.

TSTF-10 R1 Pending 3.1 NI Not incorporated based on inconsistencies with other LCOs. -- --

TSTF-11 R1 Rejected 3.1.5 N1 Not incorporated based on being rejected. -- --

TSTF-12 R1 Approved 3.0.7 F N/A C, C3 3.1 F N/A C3 C,

O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 2 of 11)

W A SPECS ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL (1) 4 TSTF-13 R1 Approved 3.1.3 FE Editorial changes made in Bases consistent with other Bases C2 C3 discussions of Notes.

TSTF-14 R3 Pending 3.1.8 F N/A C, C, TSTF-15 R1 Pending B 3.1.5 F N/A --

C3 TSTF-16 R1 Pending 3.8.9 P Plant design dictates minor changes in Bases and not C, C, adopting LCO 3.8.9 Condition C changes.

TSTF-17 R1 Pending 3.6.2 FE Revised Bases due to Byren/Braidwood 18 month fuel cycle. C, C, TSTF-19 Pending 1.1 F N/A C, --

3.3 P Changes to SR 3.3.1.12 w re not made since the SR is not --

C,/P.

applicable to the station.

TSTF-20 Pending 3.9.7 F N/A C3 C, TSTF-21 Pending 3.9.6 F N/A C,/ P.

C,/ P,,

Proposed R1 TSTF-22 Pending 3.9.5 F N/A C, --

3.9.6 TSTF-23 R1 Approved B 3.9.3 P Included requirement fcr visual indication of SRs; deleted --

C3 /F, requirement for audible count rate.

TSTF-24 Pending 3.2.3 F N/A C, --

TSTF-25 Pending 3.2.4 F N/A C, C, TSTF-26 Approved 3.4.2 F N/A C, C, TSTF-27 R1 Pending 3.4.2 F N/A C, C, TSTF-28 Approved 3.4.16 FE Editorial enhancements nade to the Bases. Ca C3

O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 3 of 11)

EDITORIAL 7,Q [SCs ST TUS EXPUM4ATION CF INCORPORATION STATUS

,)

(1) t i

TSTF-29 Rejected 3.7 NI Incorporated plant specifically. P, P, TSTF-30 R1 Pending 3.6.3 P Incorporated as applicable (some Bases changes to Actions C, C, i are not applicable to Eyron and Braid *y)d design)

TSTF-36 R2 Pending 3.3.8 FE Plant specific editorial enhancements made to the Bases due C, C, to the deletion of the second Note and to be consistent with i other Bases Note discussions.

3.8 F N/A C3 C3 3.7.13 FE Editorial enhancenent ta the Bases Note discussion. C, C3 i TSTF-37 Pending 3.3.3 el Incorporated plant specifically. -- --

~

3.8.1 hI , Incorporated plant specifically. -- --

5.6 NI Incorporated plant specifically. -- --

TSTF-38 Approved 3.8 NI Superseded by TSTF-115. -- --

TSTF-39 R1 Pending 1.1 F N/A C, --

l t

, TSTF-44 Pending 3.6.3 P Revision 0 included SG PORVS and MSSVs whose Containment C3 /B, C3/P3 Proposed R1 Isolation Valve function is to close (Section 3.6) versus the System function which is to open (Section 3.7).

Therefore, these v)lves were not included in the proposed Note in 3.6.3. Byron and Braidwood CTS do not include MSIV ;

CIV requirements. Therefore. the MSIVs were not included in i the Note. i i

3.7.1 Byron and Braidwoof CTS do not include MSIV CIV P --

C /B, 3.7.3 requirements. The efore, the changes to the MSIV Bases are l 3.7.4 not included. *

+

TSTF-45 R0 Pending 3.6 F N/A C3 C3 ;

i 4

- __ _ . _ _ . _ _ _ . . _ _ _ _ _ _ . _ _ - . . _ . _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . . ~ , , ~ . . - _ . - , - - . . ,

,m ,y b b Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 4 of 11)

ST S SS EXPLANATION OF INCORPORATION STATUS EDITORIAL A S SPECS (1) f TSTF-46 R0 Pending 3.6 F N/A C, C.

TSTF-51 Pending Various NI Not incorporated based on current licensing bases provide -- --

adequate allowance for containment penetrations during refueling.

TSTF-52 Pending 1.1 FE Added as editorial. Cu --

B 3.0 F N/A --

C /B, 3.6 P Editorially revised 3.6 Bases (= signe) and incorporated as C3 C3 pertinent to Byron and Braidwood desisa.

5.5 FE Editorially revised Section 5.0 (= signs and acceptance Cs/Pu --

criteria). Incorporated plant specific CTS air lock acceptance criteria.

TSTF-54 R0 Pending B 3.4.13 P Revised to replace the term " identified" with the term --

C, "unidenti fied. "

TSTF-60 Approved 3.4.15 NI Contradicts Condition D for entering LC0 3.0.3. -- --

TSTF-61 Approved 3.4 F N/A Cn --

TSTF-64 Pending 1.1 F N/A C, --

TSTF-65 Pending 2.0 NI Section 2.0 change superseded by TSTF-5. Some ISTF changes -- --

were superseded by plant specific nomenclature / preferences and some were not applicable depending upon which bracketed option was chosen.

5.0 P Some TSTF changes were superseded by plant specific C1 --

nomenclature / preferences and some were not applicable depending upon which bracketed option was chosen.

TSTF-68 R0 Pending 3.9.4 NI Requires plant specific calculation to support. -- --

m ,--, <-

U Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 5 of 11)

GENE C S W ,

ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL (1)

TSTF-70 Approved 3.7.16 NI See Section 3.7 DOC A3 . -- --

TSTF-71 Pending B 3.0 NI A plant specific example may be better placed in the Bases. -- --

TSTF-86 Rejected 5.2 NI Not incorporated based on being rejected. -- --

TSTF-87 R1 Pending 3.4.5 P Specified the Required Action as " Initiate action to Cu /P, 3 Cu 3.4.9 place. " rather than " Place. .." on an "Intnediate" frequency.

TSTF-88 Pending T 1.1-1 F N/A C, --

TSTF-89 Approved 3.1.7 FE Plant specific editorial enhancement. C, C, TSTF-90 Pending 3.5.3 P Retained Operating SRs consistent with CTS. C, C, TSTF-91 Pending 3.3.5 P Bracketed Trip Setpoints moved to Bases. C3 C3 TSTF-92 R0 Pending 3 9.4 NI The proposed change does not fully address the problem. This -- --

issue is covered per the word " required" in the SR. The issue is related to LCO 3.3.6 and LC0 3.9.4.

TSTF-93 Pending 3.4.9 FE Plant specific editorial enhancements made to the Bases. C3 C3 TSTF-94 Pending 3.4.9 NI TSTF only provides brackets for wording that was -- --

incorporated per CTS TSTF-95 Approved 3.2.1 F N/A C3 C3 3.2.2 TSTF-96 Approved 3.9.3 F N/A Cs C.

TSTF-97 Approved 3.2.1 F N/A C, C, TSTF-98 R1 Approved 3.2.1 FE Plant specific editorirl enhancement made to the LCO to C3/P3 C3 reference the COLR.

TSTF-99 Approved 3.2.1 F N/A C, C,

O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 6 of 11)

GENE K W pECs ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL (1)

TSTF-100 Approved 3.7.4 F N/A C, --

TSTF-101 Approved 3.7.5 F N/A C, C, TSTF-102 R0 Pending 3.7.2 P LCO JFD 3P combines the fctions which makes the proposed C,/P3 C,/P3 3.7.3 changes to LCO 3.7.3 Concitions B and C unnecessary.

TSTF-103 Pending 3.0.4 F N/A C,/P, C, TSTF-104 Pending 3.0.4 F N/A C, C, TSTF-105 Pending 3.4.1 FE Editorial enhancement made to proposed insert. C, C, TSTF-106 R1 Approved 5.0 NI Not incorporated due to inconsistencies with 3.8 Bases. ---- --

TSTF-107 Pending 3.1 FE Editorial change made to proposed insert. C, C, TSTF-108 Pending 3.1.B F N/A Cu Cu 3.4.19 NI LC0 3.4.19 RCS Loops-Test Exceptions

is for Near Term P3 P3 Operating License plants TSTF-109 Approved 3.2.4 F N/A C, C, TSTF-110 R1 Pending 3.1.4 F N/A C, 1 Ca 3.1.6 3.2.3 F N/A C, C, 3.2.4 TSTF-111 Pending B 3.3.1 F N/A --

C, B 3.3.2 TSTF-112 Pending 3.2.3 F N/A C, C, 1

l TSTF-113 R1 Pending 3.4.11 F N/A Cu Cu l

TSTF-114 Pending 3.4.7 FE Editorial enhancements made to the Bases. --

Cu /P3 l

l

\ C/ V-Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 7 of 11)

WOG ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL ST SPECS ,) ,

(1)

TSTF-115 Pending 3.8 P Some 3.8.4 Bases modifications are not applicable due to C,/C, C,/C,/P, plant specific design. Py 5.0 FE Some 3.8.4 Bases modifications are not applicaole due to C.

plant specific design.

TSTF-116 Pending 3.4.13 FE Editorial enhancement made to clarify the intent of steady C,/Pn C,/Pu 3.4.15 state operation.

TSTF-117 Pending 3.5.1 P Plant Specific deletion of details in SR 3.5.1.6. C,/P, C,/ P. ;

(WOG-57)

TSTF-135 Pending 3.3 P Various plant specific changes were made (marked against C1 C, (WOG-58) clean copy of WOG-58).

TSTF-136 Pending 3.0.7 F N/A C, C, (WOG-59) 3.1 FE Changes made consistent with the incorporation of TSTF-12. C, C, Revision 1 changes.

TSTF-151 Fending B 3.4.11 F N/A --

C, 3 (WOG-61)

TSTF-152 Pending 5.6 F N/A C.

i (WOG-65)

TSTF-153 Pending 3.4.5 F N/A C, 3 C, 3 (WOG-63) 3.5.2 P LCO Note 2 was deleted plant specifically. C3/B3 C3 /Pn 1/P, BWR-06. Pending 1.0 F Submitted as NRC editorial. C3 /C, --

C.3. R1 (2)

BWR-11. Pending 2.0 F Submitted as NRC editorial. --

C, C.10. R1 (2)

p p V \ V Attachment 4 PENDING AND PROPOSED ISTS CNANGE TRAVELERS (page 8 of 11)

ST S EXPLANATION OF INCORPORATION STATUS TU S Cs EDITORIAL (1)

WOG-21 Withdrawn 3.4.1 F This change was pending at time of development; but later C, C, withdrawn.

WOG-51 R1 Pending 3.4 P Plant specific changes were made consistent with Current C,/Pu /P 3 C,/P /P , 3 Licensing Basis. d3 n WOG-56 Withdrawn 5.0 P Proposed changes to Specification 5.2.2.e are not required C2/83 --

(BWOG-13) due to wtiich bracketed option was chosen.

WOG-60 Pending 3.4 P Editorial enhancements made to the Bases. Cu C33 WOG-62 Pending 3.8 FE Editorial enhancements made to the Bases. C,/P33 C3/P y WOG-64 Pending 3.7 FE Editorial change to add separate condition entry for C, C, Condition C consistent with Condition D.

WOG-66 Pending 3.3 P Modified Table 3.3.6-1 footnote. C, C.

Editorial enhancements made to the Bases.

WOG-67 Pending NI See TSTF-4 R1 -- --

WOG-68 Pending 3.4 F N/A --

Cy WOG-69 Pending 3.8 P Proposed changes to SR 3.8.1.2 not needed because. SR Cn /P,3 3.8.1.2 and SR 3.8.1.7 are applicable to Byron and Braidwood.

WOG-70 Pending 3.8 P Proposed changes to SR 3.8.1.2 not needed because. SR Cu C, 3 3.8.1.2 and SR 3.8.1.7 are applicable to Byron and Braidwood. Change to SR 3.8.1.2 to delete standby is editorially moved to WOG-71.

WOG-71 Pending 3.8 FE Proposed change to SR 3.8.1.2 to delete standby is Cu --

editorially added to WOG-71 WOG-72 Pending 5.0 FE Editorial enhancement made to description. C, --

t a-_.--- - - - . - . .- _ . - - - - - _ - - - - _ - - - - - _ _ - - - -

,9 -

p L] ,

L.)

Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 9 of 11)

GENE S O S W ,

ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL (1)

WOG-73 Pending 3.1 FE Editorial enhancement made to the LC0 to replace " position Cu/P,, Cu indicators" with "DRPI" WOG-74 Pending 1.0 FE Editorial enhancement made to correct gramar. C, 1 WOG-75 Pending 3.2 P Incorporated plant specific corrections in the LCO and plant C, 3 Cu specific editorial changes in the Bases. The changes explicitly state the power bands to which they apply.

WOG-76 Pending 3.9 NI Requires a plant specific calculation to implement. -- --

WOG-77 Pending B 3.0 F N/A --

C, 3 WOG-78 Pending 3.0 F N/A C, --

WOG-79 Pending 5.0 NI Incorporation of inadvertent would be less restrictive than -- --

CTS and was not justifiable.

WOG-80 Pending 3.3 P Changes made consistent with incorporation of TSTF-135 C3 C, changes.

WOG-81 Perrding 3.1 F N/A Cu --

3.3 F N/A C, --

3.4 F N/A C13 --

3.5 F N/A C, --

3.7 F N/A C, --

3.8 F N/A C;, --

3.9 F N/A C, --

WOG-82 Pending 3.3 NI Not incorporated based on the lack of technical -- --

justification.

O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVELERS (page 10 of 11)

GENE S W ST S EXPLANATION OF INCORPORATION STATUS EDITORIAL g , ,)

(1)

WOG-83 Pending 3.7 P Bases changes to SR 3.7.1.1 are not applicable to Byron and C3 /B y /B, C,/Bn 8

Braidwood (See LC0 JFD P,).

Editorial-1 Pending B 3.1 F N/A --

C,1 B 3.2 F N/A --

C3 8 3.3 F N/A --

C, B 3.4 F N/A --

C,1 B 3.5 F N/A --

C, B 3.6 F N/A --

C7 B 3.7 F N/A --

C, B 3.8 F N/A --

C, B 3.9 F N/A --

C3 Editorial-2 Pending B 3.1.1 P Superseded by plant specific changes. --

P,/P, Editorial-3 Pending 3.2.4 F N/A Cu C,3 Editorial-4 Pending 3.3 NI Technically incorrect. Incorporated proposed Editorial-4 RI. B, --

Editorial-5 Pending 3.3 NI Superseded by plant specific changes. P3 P3 ,Py

l O O O Attachment 4 PENDING AND PROPOSED ISTS CHANGE TRAVEL.ERS (page 11 of 11)

' O SES W A S S Cs ST S EXPLANATION OF INCORPORATION STATUS

,)

EDITORIAL (1)

Editorial-6 Pending 3.8 P Changes to 3.8.6 Bases scperseded by TSTF-115. C, C, Editorial-7 Pending 5.0 F N/A C, --

Editorial-8 Pending 3.5 NI Superseded by plant specific change. B, --

Table Notations:

(1) F - Fully Incorporated FE - Fully incorporated with editorial enhancements P - Partially incorporated NI - Not incorporated (2) The TSTF numbers refer to NUREG-1431. Revision 0 generic changes which were not correctly incorporated into NUREG-1431. Revision 1.

O i

l

)

i 4

ATTACHMENT 5 4

"BEYOND SCOPE" CHANGES

. O i

I l

O 1

,m , ,

U b,m Attachment 5

BEYOND SCOPE" CHANGES (page 1 of 2)

No. ITS CTS EXPLANATION OF CHANGE CTS LCO DOC JFD 1 LCO 3.1.5 Condition B LCO 3.1.3.5 Changed the Required Action for not meeting LCO to agree with the M. P3 Applicability.

2 LCO 3.1.7 LCO 3.1.3.2.a Deleted Action to "imediately" verify the position of the non- Au Pn indicating rod after any motion which exceeds 24 steps, based on the existing Action to verify position for non-indicating rods every B hours.

3 LC0 3.3.2 Table 3.3-3 Changed the Completion Time for declaring associated AF pump L, P3 Condition M Action 15a inoperable from immediately to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

4 SR 3.3.9.7 SR 4.1.2.7.a The SRM Surveillance is revised to allow the Surveillance to be Lu P,3 Table 4.3-1 performed after entering the Mode of Applicability. This is consistent with allowances provided in SR 3.3.1.7 and SR 3.3.1.8.

5 SR 3.4.1.4 Note SR 4.2.3.5 Changed the Surveillance Frequency exception from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to 7 M3 P3 days (NUREG). and from unspecified to 7 days (CTS).

6 LCO 3.4.3 LC0 3.4.9.1 Revised P/T Limits Action for P/T Limits not within Specification L, P.,

to place the unit in MODE 5 rather than in MODE 5 with RCS pressure

< 500 psig.

7 LCO 3.4.18 LCO 3.4.1.5.2 Revised the standard by which the isolated loop is compared to la P 31 allow opening of the isolation valves. This change requires the isolated loop boron concentration to be greater than or equal to the " required shutdown margin boron concentration." rather than the operating loop boron concentration.

8 SR 3.4.18.2 SR 4.4.1.5.2.2 Changed Surveillance Frequency from 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for La P, verifying boron concentration prior to opening an loop stop isolation valve.

9 LCO 3.5.5 LCO 3.4.6.2.e Changed the limits for seal injection ficw. CTS and NUREG specify L. P, a unique value. Byron and Braidwood specify a range of values in Figure 3.5.5-1.

t> 0 V Attachment 5 "BEYOND SCOPE" CHANGES (page 2 of 2)

No. ITS CTS EXPLANATION OF CHANGE CTS LCO DOC JFD 10 LCO 3.6.3 LCO 3.6.1.7 Added clarification that deactivated remote manual valves can A3 P, satisfy the Required Action for an inoperable containment isolation valve to be isolated.

11 LCO 3.8.1 LC0 3.8.1.1 Revised Required Action for loss of 2 offsite circuits to one bus L3 Py and loss of the associated DG from enter LCO 3.0.3 to restore in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

12 SR 3.8.1.8 SR 4.8.1.1.1.b Deleted the "during shutdown" aspect of the SRs. (Deleted ITS Note L3 Pn that indicates "This Surveillance shall not be performed in MODE 1 SR 3.8.1.12 SR 4.8.1.1.2.f.5) or 2".) L,, Pg SR 3.8.1.13 SR 4.8.1.1.2.f.6) 13 SR 3.8.1.10 SR 4.8.1.1.2.f.3) Added Note such that momentary transients above the DG full load L,2 P,,

reject voltage limit do not invalidate the test 14 LC0 3.9.4 LC0 3.9.4 Added Surveillance Requirement to verify purge valve isolation % P3 times.

15 Specification 5.5.11 LCO 3.7.6 Added clarification that the Ventilation Filter Testing Program L, P.

LCO 3.7.7 tests may be in " general conformance with" Regulatory Guide 1.52.

LCO 3.9.12 16 Specification 5.5.16 SR 4.6.1.2 Added exception to NEI 94-01 in CTS Section 3.6 to allow the L. C3 elapsed time between consecutive satisfactory Type A tests to be a 18 months rather than a 24 months.

17 Specification 5.7 Specification 6.12 Revised High Radiation Area Specification to reflect the most L, Pu current 10 CFR Part 20.

I 1

4 i

10 1

i J

k i

i 1

! ATTACHMENT 6

BEYOND SCOPE BRACKETED" CHANGES

!O d

i i

3 l

1 r

1 i

i i

1

?

i 1

i e

+

, , . , ~ . . - ..---,.-..-.,ee. .

. . . ,n--- - - --,.. . -------.---,-.-n.. ,, - . . -.. , -. - ,..-. --. - - -- - - - - - ,- -._.

p im Y J Attachment 6 BEYOND SCOPE BRACKETED CHANGES (page 1 of 1)

No. ITS CTS EXPLANATION OF CHANGE DOC 1 LCO 3.2.1 LC0 3.2.2 Changed current licensing basis methodology used to determine Power L, Distribution Limit (Heat Flux Hot Channel Factor).

2 SR 3.4.5.2 SR 4.4.1.3.2 Changed low low SG Water Level values consistent with Rx Trip L3 SR 3.4.6.2 setpoints.

SR 3.4.7.2 3 LC0 3.7.12 LC0 3.7.7 (Braidwood Only) Modified SRs such that HVAC bank flow rates need L,,

only be measured after structural housing maintenance.

Specification 5.5 L3 4 SR 3.8.1.3 SR 4.8.1.1.2.a.5) Change DG loading values; in confonnance with Regulatory Guide 1.9. L3 SR 3.8.1.10 SR 4.8.1.1.2.f.3) [3 SR 3.8.1.14 SR 4.8.1.1.2.f.7) & L3 /L, 2

Footnote

SR 3.8.1.15 SR 4.8.1.1.2.f.7) & L 27 Footnote **

5 LCO 3.8.1 SRs SR 4.8.1.1.2 SRs Revised acceptable voltages from 4160 V 420 V to 3950 V to M, 4580 V.

O ATTACHMENT 7 CTS REQUIREMENTS RELOCATED O TO OTHER LICENSEE CONTROLLED DOCUMENTS i

l 1

l

O 5

l Attachment 7 O CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS U (page 1 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 2.0 SAFETY LIMITS LA3 The requirement to notify the NRC within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TRM"' 10CFR50.59 following violation of a Safety Limit.

LA, The requirement to notify the Vice President PWR TRM"' 10CFR50.59 Operations and the Offsite Review and Investigation Function within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following violation of a Safety Limit.

LA3 The requirement to prepare, review, and submit a UFSAR 10CFR50.54(a)

Safety Limit Violation Report within 14 days to the Chapter 17 i NRC, appropriate management personnel, and plant I safety committees following a Safety 1.imit violation. l LA, The requirement to obtain authorization by the TRM"' 10CFR50.59 Commission prior to critical operation of the unit following a Safety Limit violation, ITS SECTION: 3.0 LC0 AND SR APPLICABILITY LA, The Applicability requirements providing guidance for TRM"' 10CFR50.59 dual unit operation to clarify each LC0 applicability O or surveillance activity.

b ITS SECTION: 3.1 REACTIVITY CONTROL SYSTEMS R3 The requirement associated with establishing the TRM"' 10CFR50.59 controls for shutdown margin in MODES 1 and 2 with k,,, a 1.0.

R, The requirement associated with establishing the flow TRM"' 10CFR50.59 path controls for the boration subsystem of the Chemical and Volume Control System in MODES 4. 5.

and 6.

R3 The requirement associated with establishing the flow TRM"' 10CFR50.59 path controls for the boration subsystem of the Chemical and Volume Control System in MODES 1. 2.

and 3.

R. The requirement associated with establishing the TRM"' 10CFR50.59 charging pump controls for the boration subsystem of the Chemical and Volume Control System in MODES 4. 5.

and 6.

R. The requirement associated with establishing the TRM"' 10CFR50.59 charging pump controls for the boration subsystem of the Chemical and Volume Control System in MODES 1, 2.

and 3.

R, The requirement to establish the controls for the TRM"' 10CFR50.59 control rod position indicating system in MODES 3. 4 l

/ and 5 when the reactor trip breakers are closed and V] during performance of rod drop time measurements.

l

1 Attachment 7 O CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS V (page 2 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.1 REACTIVITY CONTROL SYSTEMS (continued)

LA The specific values associated with Shutdown Margin COLR"' 10CFR50.59 supporting reactivity control.

LA, Details which specify the required boration flow rate TRM"' 10CFR50.59 and boric acid solution concentration associated with the method of restoring Shutdown Margin compliance.

LA3 Procedural details describing the reactivity factors Bases Bases Control taken into consideration when performing a reactivity Program balance calculation.

LA, Details associated with the administrative control Bases Bases Control bank withdrawal limits which are established when Program Moderator Temperature Coefficient is more positive than the beginning of life Moderator Temperature Coefficient limit.

LA3 The requirement to submit a Special Report within TRM"' 10CFR50.59 10 days to the NRC in the event Moderator Temperature Coefficient is more positive than the beginning of life limit specified in the Core Operating Limits Report, ,

LA, Descriptive information associated with two possible Bases Bases Control examples of what could render a control rod Program '

immovable.

1 LA, Descriptive information associated with an Bases Bases Control l alternative approach for the restoration of a Program misaligned rod. l LA, Details associated with the list of accident analyses UFSAR 10CFR50.59 to be addressed in the re-evaluation in the event of

an inoperable but trippable rod have been relocated.

LA, The requirement associated with a more frequent TRM"' 10CFR50.59 .

performance of the rod position or control bank (

surveillance when the rod position deviation alarm is ,

inoperable. I LA3 , The requirement associated with performing a rod drop TRM"' 10CFR50.59 test for affected rods following any maintenance on or modification to the Control Rod Drive System.

LA u Descriptive information associated with the Bases Bases Control requirements which must be met for the control rod Program positic, indicators to be Operable.

LA3 , The requirement a ciated with verifying that each TRM"' 10CFR50.59 shutdown bank is within the insertion limit specified in the Core Operating Limits Report within 15 minutes n prior to withdrawal of any control bank rods during (d) an approach to criticality. I i

Attachment 7 p

V CTS REQlllREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (page 3 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.1 REACTIVITY CONTROL SYSTEMS (continued)

LAu Details associated with the method of establishing Bases Bases Control compliance and restoring the control banks to within Program limits by reducing thermal power consistent with rod position.

LAy Details associated with the method for verifying the Bases Bases Control Heat Flux Hot Channel Factor and the Nuclear Enthalpy Program Rise Hot Channel Factor are within limits.

LA 3 The rcquirement associated with establishing the TRM"' 10CFR50.59 borated water source controls for the Boric Acid Storage System and the Refueling Water Storage Tank.

LA a The requirement associated with performing additional TRM"' 10CFR50.59 Shutdown Margin verifications af ter detection of an inoperable control rod (s) in Mode 2 with k,,, < l.0 and Modes 3, 4. and 5.

LA g Details associated with the initial conditions for TRM"' 10CFR50.59 verifying core reactivity. ,

,G ITS SECTION: 3.2 POWER DISTRIBUTIOd LIMITS LA Details associated with the method for confirming the Bases Bases Control normalized symmetric power distribution during the Program Quadrant Power Tilt Ratio surveillances.

LA, Details associated with the Heat Flux Hot Channel Bases /COLR"' Bases Control Factor limit. Prgram/

10CFR50.59 LA 3 Details associated with the Nu; lear Enthalpy Rise Hot Bases /COLR"' Bases Control Channel Factor limit. Prgram/

10CFR50.59 LA4 Details associated with the optional method in which Bases Bases Control the target flux difference may be determined during Program an Axial Flux Difference surveillance.

LA, The Heat Flux Hot Channel Factor and Nuclear Enthalpy TRM"' 10CFR50.59 Rise Hot Channel Factor requirement to identify and correct the cause of the out of limit condition prior to increasing thermal power.

LA, The requirement to provide conditional surveillances TRM"' 10CFR50.59 whenever the Axial Flux Difference monitor alarm and Quadrant Power Tilt Ratio monitor alarm are Inoperable.

A

Attachment 7 7

T CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS

\ (page 4 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.2 POWER DISTRIBUTION LIMITS (continued)

LA, Details associated with the method for determining Bases Bases Control the target flux difference during surveillance. Program LA, Details associated with demonstrating that the Heat Bases Bases Control Flux Hot Channel Factor is returned to within limits Program after corrective actions have been taken through incore flux mapping.

ITS SECTION: 3.3 INSTRUMENTATION R The requirement to ensure the Operability of the TRM"' 10CFR50.59 Movable Incore Detector Instrumentation for use in monitoring the flux distribution within the core.

R, The requirement to ensure the Operability of seismic TRM"' 10CFR50.59 instrumentation used to record data for use in evaluating the effect of a seismic event after the occurrence of such an event.

R3 The requirement to ensure the Operability of TRM"' 10CFR50.59 meteorological instrumentation used to record meteorological data for use in evaluating the effect

(

e of an accidental radioactive release from the plant.

R. The requirement to ensure the Operability of loose TRM"' 10CFR50.59 part detection instrumentation used to detect loose parts in the Reactor Coolant System which could cause j damage to components in the Reactor Coolant System. l R3 The requirement to ensure the Operability of TRM"' 10CFR50.59 high-energy line break isolation sensors used to detect and initiate protective actions in the event l of a line break. l

, R. The requirement to ensure the Operability of turbine TRM"' 10CFR50.59 overspeed protection instrumentation used to trip the turbine to prevent the generation of potentially l damaging missiles from the turbine, in the event of a loss of the turbine speed control system, or a transient.

R, The requirement to ensure the Operability of the TRM"' 10CFR50.59 explosive gas monitoring instrumentation for maintaining the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System below the flammability limit of hydrogen and oxygen.

LA, Details of the valves to be closed and the method of Bases Bases Control isolating the unborated water source flow paths in Program the event of a Boron Dilution Prevention System j] inoperability.

V

1 Attachment 7 )

/] CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS V (page 5 of 22) doc ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.3 INSTRUMENTATION (continued)

LA, Details of Source Range Monitor Operability Bases Bases Control supporting the Operability of the Boron Dilution ,. Program Protection System.

LA3 Allowable Values for the Loss of Power ESF Bus Bases Bases Control Undervoltage and Degraded Grid Voltage Functions. Program LA, Details associated with the Reactor Trip System and Bases /TRM'" Bases Control Engineered Safety Feature Actuation System interlock Program /

function requirements and the descriptive information 10CFR50 59 for each interlock function.

LA, Design details associated with the Reactor Trip Bases /UFSAR Bases Control System and Engineered Safety Feature Actuation System Program /

functions. 10CFR50.59 j LA, Details associated with the Reactor Trip System. 00CM/TRM ITS ODCM Engineered Safety Feature Actuation System, and Program /

Containment Ventilation Isolation Instrumentation 10CFR50.59 trip setpoints.

O LA, Details associated with the Reactor Trip System and Engineered Safety Feature Actuation System Bases Bases Control Program ij instrumentation allowable values.

1 LA, Details associated with the Boron Dilution Protection Bases Bases Control !

System test acceptance criteria for an actuation Program l test.

LA n Details associated with performing Channel Bases Bases Control Calibrations on the Intermediate Range Monitor and Program Source Range Monitor instruments.

LA u The requirement to perform a Trip Actuating Device TRM'" 10CFR50.59 l Operational Test following maintenance or adjustment i of the Reactor Trip Breakers.

LA u Details associated with the description of the Bases Bases Control Engineered Safety Feature Actuation System Program instrumentation design.

LA g The requirement to maintain the Engineered Safety TRM'" 10CFR50.59 Feature Actuation System function for individual manual isolation of the main steam isolation valves.

LA 3 The requirement to maintain the Er.gineered Safety TRM'" 10CFR50.59 Feature Actuation System function for manual initiation of the auxiliary feedwater pumps.

(s

Attachment 7

(~ CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (page 6 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.3 INSTRUMENTATION (continued)

LA3 Details of performing Channel Calibrations on the Bases Bases Control Steam Line Pressure - Low and Steam Line Program Pressure - Negative Rate - High Engineered Safety Feature Actuation System Functions.

LAg Instrument numbers associated with the Fuel Building Bases Bases Control isolation, Containment Isolation and Main Control Program Room Isolation Radiation Monitoring Functions.

LA 3 The requirement to submit a Special Report within TRM"' 10CFR50.59 30 days to the NRC following the inability to restore the Main Control Room isolation Radiation Monitoring Function to an Operable status.

LA n Details and requirements associated with for the TRM"' 10CFR50.59 operation of the crane with loads over the fuel storage pool.

LA3 Design attributes associated with the Fuel Handling Bases Bases Control Building Exhaust filter Plenum Ventilation System. Program O LAn The requirement to provide a portable continuous TRM"' 10CFR50.59 monitor with the same alarm setpoint in the fuel pool 1] area whenever both fuel handling building isolation channels are inoperable.

LAn Design attributes associated with the Remote Shutdown Bases Bases Control System. Program LAn The listing of Remote Shutdown System Functions. Bases Bases Control Program LA3 The requirements associated with the Accident TRM"' 10CFR50.59 Monitoring System Functions which are not classified as Regulatory Guide 1.97. Type A and Category I variables.

LA3 Details associated with the design of Engineered Bases Bases Control Safety Feature Actuation System functions. Program LA3 Details associated with the method of performing Bases Bases Control Channel Calibrations on the Post Accident Program Monitoring - Containment High Range Area Radiation instruments.

O

1 l

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS

(~}

V (page 7 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL l l

ITS SECTION: 3.3 INSTRUMENTATION (continued)

LA,, The requirement to perform an analog Channel TRM"' 10CFR50.59 Operational Test every 92 days on the hydrogen monitor and a requirement to check that the hydrogen monitor is in a standby mode.

LA3 Details associated with the method of performing Bases Bases Control Channel Calibrations on the Hydrogen Monitor Program instrumentation.

LA 3 Design attributes associated with the Remote Shutdown TRM"' 10CFR50.59 System.

LA3 Details of the methodology for Trip Actuating Device Bases Bases Control Operational Testing of the Reactor Trip Breakers. Program Reactor Trip Bypass Breakers, and the associated shunt trip and undervoltage trip mechanisms.

ITS SECTION: 3.4 REACTOR COOLANT SYSTEM (RCS)

R, The requirement for a minimum of one pressurizer Codc TRM"' 10CFR50.59 safety valve to be Operable in Modes 4 and 5.

U R, The requirement to ensure that the Reactor Coolant TRM"' 10CFR50.59 System chemistry is maintained within prescribed limits to minimize corrosion.

R3 The requirement to ensure pressurizer temperature TRM"' 10CFR50.59 l maximum heatup and cooldown rate limits to prevent nonductile failure and to assure compatibility of operation with the fatigue analysis.

R, The requirement to ensure the structural integrity of TRM"' 10CFR50.59 ASME Code Class 1. 2. and 3 components are maintained in accordance with Section XI of the ASME Code.

Rs The requirement to ensure the Operability and closure TRM"' 10CFR50.59 of at least one reactor head vent path whenever the unit is in Mode 1, 2. 3, or 4.

LA, Descriptive information associated with the operating Bases Bases Control verification of the reactor coolant loops. Program LA, Details associated with the components that Bases Bases Control constitutes Reactor Coolant System loop Operability. Program LA3 Descriptive information associated with the operating Bases Bases Control l verification of the Reactor Coolant System and Program Residual Heat Removal loops.

l l

l

/] i 1

1 Attachment 7

(]

V CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (page 8 of 22) ;

DOC ISSUE RELOCATEL' DOCUMENT CONTROL ITS SECTION: 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

LA4 Details associated with the components that Bases Bases Control constitutes Reactor Coolant System and Residual Heat Program Removal loop Operability.

LA, Details associated with the testing method used to Bases Bases Control demonstrate pressurizer heater Operability. Program LA, Details associated with the testing method for Bases Bases Control verifying reactor coolant gross specific activity. Program LA, The requirement for Channel Calibration testing of TRM"' 10CFR50.59 ;

the Power Operated Relief Valve actuation instrumentation.

LA, Details associated with for performance of the action Bases Bases Control )

to analyze containment atmosphere (analyzed for Program j gaseous and particulate radioactivity).

LAa Details associated with the Reactor Coolant System TRM"I 10CFR50.59 Pressure Isolation Valve test performance for various ,

unit conditions. l O l Q LA n The listing of Reactor Coolant System Pressure Isolation Valves.

Bases Bases Control Program LA 3 Details associated with the specific demonstration Bases Bases Control ensuring Safety injection and charging pumps are Program incapable of injecting into the Reactor Coolant System during Low Temperature Overpressure Protection conditions.

LA 3 Details associated with specific valve identifiers Bases Bases Control l for the Residual Heat Removal suction valves and Program Residual Heat Removal suction relief valves.

1 LAi , Details associated with descriptive information for Bases Bases Control !

operation of four reactor coolant loops. Program LA3 Details associated with the method for determining TRM"' 10CFR50.59 the Reactor Coolant System total flow rate.

LA n The requirement to perform a Channel Calibration TRH"' 10CFR50.59 every 18 months on the Reactor Coolant System total flow rate indicators.

LA3 Details associated with a pressurizer tenperature Bases Bases Control notation associated with the Reactor Coolant System Program Pressure and Temperature LC0 limits.

i 4

O

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS s_./ (page 9 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

LA,, Descriptive information associated with the condition Bases Bases Control of the operating steam generators during the Program determination of Reactor Coolant System operational leakage.

LA,, Details associated with the performance of an Bases Bases Control engineering evaluation for determining the Program acceptability of the Reactor Coolant System for continued operation.

LAn The requirement to verify that the oil separator TRM'" 10CFR50.59 portion of the containment floor drain collection sump has been filled to the level of the overflow to the containment floor drain collection weir box.

LA3 The requirements for determining Reactcr Coolant T RM'" 10CFR50.59 System leakages through monitoring of the containment atmosphere radioactivity, reactor cavity sump discharge the containment floor drain sump discharge and inventory, and the reactor head flange leakoff.

A LA3 The requirement to submit a special report in the TRM'" 10CFR50.59 tj event that either the Power Operated Relief Valves,

\ the Residual Heat Removal suction relief valves. or the Reactor Coolant System vents are used to mitigate a Reactor Coolant System pressure transient.

LA3 The requirement to verify Reactor Coolant System TRM'" 10CFR50.59 Pressure Isolation Valve leakages for affected valves following any maintenance, repair, or replacement work prior to returning the valve to service.

LA,, Details associated with specific equipment Bases Bases Control identifiers for the containment atmosphere gaseous Program and particulate radioactivity monitors.

LA3 Details associated with the method used to determine Bases Bases Control Containment Floor Drain and Reactor Cavity Sump Flow Program Monitoring System Operability.

LA,, The requirement to verify the Reactor Coolant System TRM'" 10CFR50.59 average temperature limits once per 30 minutes when the reactor is critical and the Reactor Coolant System T , is < 557'F with the T.,-T,g Deviation Alarm notresel.

^\

(d

I i

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS

[]

V (page 10 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

Ri The requirement to ensure, when in Mode 5 and 6 with TRM"' 10CFR50.59 j the pressurizer level less than or equal to 5 4 I

percent, that a diverse means of introducing makeup water from the Refueling Wdter Storage Tank to the Reactor Coolant System are available in the event that a loss of inventory or loss of forced circulation occurs which results in a loss of decay heat removal.

LA Details associated with the method of removing power Bases Bases Control from each Emergency Core Cooling System accumulator Program valve operator.

LA, The requirement to perform a Channel Calibration TRM"' 10CFR50.59 every 18 months for the accumulator water level and pressure channel.

LAa Details associated with describing an Operable Bases Bases Control Emergency Core Cooling System subsystem and flow Program path.

LA, The requirements (1) to prepare and submit a Special TRM"' 10CFR50.59 O

Report to the NRC within 90 days whenever the Emergency Core Cooling System is actuated and injects water into the Reactor Coolant System and (2) to provide the usage factor for each affected Safety injection nozzle whenever its value exceeds 0.70.

LA, Details associated with specific equipment Bases Bases Control identifiers and descriptive information associated Program with isolation of Emergency Core Cooling System flow paths and closure of isolation valves during the performance of pressure isolation valve surveillance I testing. I LA, The requirement to ensure accumulator Operability TRM"' 10CFR50.59 during Mode 3 with pressurizer pressure < 1000 psig whenever isolation valves S!8809A or SI8809B are closed.

LA, Details describing the method used to ensure that the Bases Bases Control Emergency Core Cooling System piping is full of Program water.

LA, The requirement to ensure, by a visual inspection. TRM"' 10CFR50.59 l that no loose deb-is is present in the containment.

A h

Attachment 7 O CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS br (page 11 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) (continued)

LA, Details associated with the method for performing the Bases Bases Control Emergency Core Cooling System automatic valve Program actuation and automatic pump start surveillance tests.

LAa The listing of Emergency Core Cooling System pumps. Bases Bases Control Program LA n Details describing the pump acceptance criteria and TRM"' 10CFR50.59 test methods associated with the Emergency Core Cooling System pump performance surveillance test.

LA,, The requirement to ensure the correct position of TRM"' 10CFR50.59 each mechanical stop for certain Emergency Core Cooling System throttle valves within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completing a valve stroke operation or valve 1 maintenance.

LA n The requirement to perform a flow balance test to the TRM"' 10CFR50.59 Emergency Core Cooling System subsystems following the completion of modifications that alter the l subsystem flow characteristics. ;

LA g Details associated with position stops of the Bases Bases Control Emergency Core Cooling System throttle valves. Program LA a Details describing the Operability requirements Bases Bases Control associated with the Refueling Water Storage Tank vent Program path.

ITS SECTION: 3.6 CONTAINMENT SYSTEMS LA3 The containment isolation valve component listing has TRM"' 10CFR50.59 been relocated consistent with the direction of Generic Letter 91-08. " Removal Of Component Lists From Technical Specifications."

LA, Details associated with the Operability of the Bases Bases Control containment air lock interlock function. Program LA3 Details associated with the method of determining Bases Bases Control average containment air temperature. Program LA, Details associated with the method to ensure that the Bases Bases Control 48 inch purge valves are " sealed closed" and assured Program of not inadvertently opening.

Attachment 7 G CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS

/

d (page 12 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.6 CONTAINHENT SYSTEMS (continued)

LA, Details associated with design attributes of the Bases Bases Control Containment Spray System and details describing the Program minimum requirements for an Operable flow path.

LA, Details associated with the required developed head TRM'" 10CFR50.59 for the containment spray pump and test flow path '

during performance of the Surveillance.

LA, Details associated with the verification that the Bases Bases Control spray nozzles are unobstructed and the method used in Program performing this verification.

LA, Details associated with describing the minimum Bases Bases Control .

I requirements of an Operable Spray Additive System Program flow path. l I

LA w Details associated with the acceptance criteria for TRM'" 10CFR50.59 the flow rate verification surveillance of the Spray Additive System.

LA n Details associated with the design attributes of the Bases Bases Control

/'N containment cooling fans and details describing the Program

'y) minimum requirements for an Operable cooling train.

LA u Details associated with the method of conducting the TRM'" 10CFR50.59 containment cooling fan system surveillance.

LA n Details associated with the design attributes of the Bases Bases Control l Hydrogen Recombiner System. Program l LA 3 Details of 1) rate of heater sheath temperature Bases /TRM'" Bases Control increase and power consumption: 2) channel Program /

calibration of instrumentation and controls; 10CFR50.59

3) attributes of a visual examination; and

4) required heater phase resistance associated with specific acceptance criteria for hydrogen recombiner testing.

LA 3 The requirement to demonstrate Operability after TRM'" 10CFR50.59 maintenance or repair on an isolation valve.

LA a Details of the acceptance criteria for leakage rate TRM'" 10CFR50.59 tests associated with the containment purge valves.

LAg Details associated with the method for isolating the Bases Bases Control 48-inch purge valves. Program

Attachment 7 f' CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS b (page 13 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.7 PLANT SYSTEMS R, The requirement to ensure that the temperatures of TRM"' 10CFR50.59 thereactorandsecpndarycoolantsinthesteam generators are > 70 F when the pressure of either coolant in the steam generator is > 200 psig.

R3 The requirement to ensure that leakage from TRM"' 10CFR50.59 byproduct, source and special nuclear material sources will not exceed allowable Intake values.

R, The requirement to ensure that the temperature in TRM"' 10CFR50.59 areas of the plant which contain safety related equipment does not exceed its environmental qualification temperature during normal operation.

LA 3 Details relating to the lift setting pressure of the Bases Bases Control Main Steam Safety Valves. Program LA, Details associated with design attributes of an Bases Bases Control Operable Auxiliary feedwater System and details Program describing the minimum requirements for an Operable Auxiliary feedwater System. ,

LA 3 Details associated with the required developed head TRM"' 10CFR50.59 for the Auxiliary feedwater pumps during ;

Surveillances. ,

LA. The requirements associated with the Operability of TRM"' 10CFR50.59 the diesel portion of the diesel driven Auxiliary l Feedwater pump.

LA3 Details associated with the verification of Bases Bases Control ;

Operability of the Essential Service Water System Program when used as a backup to the Condensate Storage Tank for the Auxiliary Feedwater System.

LA. The requirements associated with the Operability of Bases Bases Control the Component Cooling Water System. Program l l

LA, The requirement associated with a monthly TRM"' 10CFR50.59 surveillance demonstrating the Operability of the Component Cooling Water System pumps.

LA, Details associated with the common Component Cooling TRM"' 10CFR50.59 Water System pump tests have been relocated.

LA, The requirement associated with the 31-day TRM"' 10CFR50.59 verification of Operability of the Component Cooling Water System heat exchanger inlet and outlet valves. .

1 i

l l

1 1

Attachment 7 f CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (l) (page 14 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.7 PLANT SYSTEMS (continued)

LA n Details associated with design attributes of the Bases Bases Control Essential Service Water System have been relocated. Program LAy Details associated with the Operability of the Bases Bases Control opposite-unit Essential Service Water System pump and Program crosstie and details associated with specific equipment identifiers for the crosstie valves have been relocated.

LA n The requirements associated with demonstrating the TRM"' 10CFR50.59 availability of the opposite-unit Essential Service Water System to support unit-specific operation have been relocated.

LA 3 For Braidwood Station only, the requirement TRM"' 10CFR50.59 associated with the performance of a hydrographic survey every 18 months to verify no degradation on the Ultimate Heat Sink.

LA 3 for Braidwood Station only, details associated with Bases Bases Control the method for determining Ultimate Heat Sink Program f temperature have been relocated.

(*

LA g Details associated with design attributes of the Bases /TRM"' Bases Control Nonaccessible Area Exhaust Filter Plenum Ventilation Program /

System and the method for demonstrating Operability 10CFR50.59 of the Nonaccessible Area Exhaust Filter Plenum Ventilation System have been relocated.

LA y Details associated with design attributes and the Bases Bases Control methods of performing surveillances of the Control Program Room Ventilation Filtration System and Control Room Ventilation Temperature Control System have been relocated.

LA w Details associated with potential causes of Control Bases Bases Control Room Ventilation Temperature Control System Program inoperability have been relocated, j LA g Details of the recirculation flow rate acceptance TRM"' 10CFR50.59 criteria associated with the Control Room Ventilation Filtration System positive nominal pressure i surveillances have been relocated.

l 1

j D

Attachment 7 ;

/g CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS V (page 15 of 22) i DOC ISSUE RELOCATED DOCUMENT CONTROL I ITS SECTION: 3.7 PLANT SYSTEMS (continued)

LAn The requirements associated with the fuel Handling TRM"' 10CFR50.59 Building Exhaust Filter Plenum Ventilation System .

Operability during the movement of new fuel or the movement of heavy loads over irradiated fuel in the fuel handling building have been relocated.

LAn Details associated with the alignment of other TRM"' 10CFR50.59 !

systems during the performance of the Fuel Handling Building Exhaust Filter Plenum Ventilation System surveillance have been relocated. l I

LAn Details associated with design attributes, the Bases /TRM"' Bases Control methods of performing surveillances, ano the method Program /

for demonstrating Operability of the of the fuel 10CFR50.59 Handling Building Exhaust filter Plenum Ventilation System have been relocated.

LA3 For Byron Station only, details associated with the Bases /TRM"' Bases Control method of verify 1ng the Operability of the deep well Program /

pumps and the requirements associated with deep well 10CFR50.59 pumps as related to the Ultimate Heat Sink p Operability have been relocated.

b LA3 For Byron Station only, the requirements associated TRM"i 10CFR50.59 with the Operability of the diesel portions of the Essential Service Water System diesel driven makeup .

pumps have been relocated. J For Byron Station only, the requirements associated TRM"' 10CFR50.59 I LA,,

with the Operability of the Ultimate Heat Sink basin i

level switches providing the automatic start signal i for the makeup pumps on low basin level have been relocated.

LA,, for Byron Station only, the requirement associated TRM"' 10CFR50.59 with visually inspecting the cooling tower fill to verify no degradation of the Ultimate Heat Sink, l LA3 For Byron Station only, details associated with Bases /TRM"' Bases Control design attributes of performing the Ultimate Heat Program /

Sink fan surveillance have been relocated. 10CFR50.59 LA3 For Byron Station only, details associated with Bases Bases Control '

Ultimate Heat Sink Operability have been relocated. Program LA3 For Byron Station only. details associated with the Bases Bases Control Ultimate Heat Sink basin level switches have been Program relocated.

l r

U l

l l

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS O.O (page 16 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.7 PLANT SYSTEMS (continued)

LA,3 for Byron Station only, the requirements associated TRM"' 10CFR50.59 with the National Weather Serv 1ce forecasts of river level and tornadoes to ensure Ultimate Heat Sink Operability have been relocated.

LA3 , For Byron Station only, the requirement to provide a TRM"' 10CFR50.59 special report to the NRC if any basin level switch is inoperable for more than 30 days.

LA33 For Byron Station only, details associated with river Bases Bases Control level and flow rate to ensure Ultimate Heat Sink Program Operability have been relocated.

LA3 Details associated with the listing of Feedwater TRM"' 10CFR50.59 Isolation Valves have been relocated.

LA,, The requirement associated with demonstrating TRM"' 10CFR50.59 Operability of a Feedwater Isolation Valve after maintenance or repair.

LA3 , Details associated with the method of isolating the TRM"' 10CFR50.59 A Feedwater Isolation Valves have been relocated.

'U LA, Details associated with placing an Operable Bases Bases Control Program Nonaccessible Area Exhaust Filter Plenum Ventilation System train in standby for the purpose of testing an inoperable train have been relocated.

LA3 , The requirements associated with the Operability and TRM"' 10CFR50.59 i testing of snubbers have been relocated.

ITS SECTION: 3.8 ELECTRICAL POWER SYSTEMS R, The requirements associated with the Operability and TRM"' 10CFR50.59 testing of containment penetration conductor overcurrent protective devices to minimize the potential for a fault in a component inside containment, or in cabling which penetrates the containment have been relocated.

R, The requirements associated with the Operability and TRM"' 10CFR50.59 testing of motor-operated valves thermal overload protection devices which minimize the potential for an improper setting of a thermal overload have been relocated.

A

(

l Attachment 7

/O V

CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (page 17 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.8 ELECTRICAL POWER SYSTEMS (continued)

LA 3 Details associated with defining the two incoming Bases Bases Control offsite AC power sources, design features of the Program diesel generators, and listing of the diesel generator fuel oil volume requirements have been relocated.

LA, Details associated with start signal options that can Bases Bases Control be used for the monthly diesel generator start Program surveillance have been relocated.

LA3 Details associated with the explicit verification Bases Bases Control that the diesel generator is aligned to provide Program standby power have been relocated.

LA, Details associated with the allowance to perform a Bases Bases Control pre lube prior to the performance of a diesel Program generator surveillance have been relocated.

LAs Details associated with the specific single largest Bases Bases Control post-accident load for the diesel generator single Program load rejection surveillance have been relocated.

A LA, Details associated with the acceptable load range for Bases Bases Control the diesel generator load run surveillance have been Program relocated.

LA, The requirements associated with a 10-second start TRM'" 10CFR50.59 and confirmation of operating voltage and frequency during the 24-hour diesel generator surveillance have been relocated.

LA, Details associated with the design for auto-connected UFSAR 10CFR50.59 loads to each diesel generator have been relocated.

LA, Details associated with the acceptance criteria for Bases Bases Control correcting specific gravity for electrolyte Program temperature and level to ensure battery Operability have been relocated.

LA w The requirement associated with verifying the ability TRM'" 10CFR50.59 to cross-tie the "A" diesel generator to the respective opposite unit's 4 kV ESF bus to ensure the ability to power a unit-specific auxiliary feedwater pump from the opposite-unit diesel generator.

LAn The requirement associated with verifying the diesel TRM'" 10CFR50.59 generator lockout features to prevent diesel generator starting only when required.

Qv

Attachment 7

( CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS (page 18 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.8 ELECTRICAL POWER SYSTEMS (continued)

LAy Details associated with the method for cleaning the TRM"' 10CFR50.59 diesel fuel storage tank and the requirement to perform a pressure test on the diesel generator fuel oil system piping have been relocated.

LAn The requirements associated with crane operation with TRM"' 10CFR50.59 loads over the spent fuel pool following a loss of power sources have been relocated.

LA y Details associated with design features and Bases /UFSAR Bases Control Operability of the DC electric sources, Instrument Program /

Buses and the Instrument Bus inverters have been 10CFR50.59 relocated.

LA3 Details associated with battery degradation criteria Bases Bases Control have been relocated. Program LA 3 The requirement associated with demonstrating 1RM"' 10CFR50.59 Operability after modifications which could affect diesel generator interdependence.

(~T ITS SECTION: 3.9 REFUELING OPERATIONS V R, The requirement associated with the communication TRM'i' 10CFR50.59 between the control room and the refueling station to ensure that any abnormal change in the facility status observed on the control room instrumentation can be communicated to the refueling station personnel.

R3 The requirements to (1) ensure that the refueling TRM"' 10CFR50.59 machine and auxiliary hoist will have sufficient load capacity for their intended purpose and will be used correctly during refueling and (2) ensure that the core internals and reactor vessel are protected from excessive lifting force during refueling operations have been relocated.

R. The requirements to ensure that loads in excess of TRM"' 10CFR50.59 the nominal weight of one fuel assembly containing a Rod Control Cluster Assembly, plus the weight of the fuel handling tool, will not be moved over other fuel assemblies stored in the spent fuel storage racks have been relocated.

LA 3 The specific value associated with the minimum boron COLR"' 10CFR50.59 concentration.

0 1

V

l i

l Attachment 7

/9 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS V (page 19 of 22)

I DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 3.9 REFUELING OPERATIONS (continued)

LA, The requirement associated with maintaining boron Bases Bases Control concentration at a limit to ensure a core k,,, of Program s 0.95.

LA3 Details associated with the method of restoring TRM"' 10CFR50.59 l boration flow rate and minimum bcron concentration have been relocated.

LA, The specific listing of unborated water source Bases Bases Control isolation valves. Program LAs Details associated with the methods for verifying Bases Bases Control that the unborated water source isolation valves are Program closed and secured in position have been relocated.

LA. The requirement associated with a time limit on TRM"' 10CFR50.59 reactor subcriticality prior to the movement of irradiated fuel assemblies.

LA, Details associated with the regions required to Bases Bases Control maintain minimum boron concentrallon have been Program relocated.

LA, Details associated with the analysis used for Bases Bases Control determining boron concentration have been relocated. Program LA, Details associated with the Operability requirements Bases Bases Control of the source range neutron flux monitors and the Program requirement that each monitor provide visual indication have been relocated. )

LA g The requirements associated with Residual Heat TRM"' 10CFR50.59 Removal loop flow rate and Reactor Coolant System I temperature for the performance of Residual Heat Removal loop testing have been relocated.

LAn The requirements associated with reactor vessel water TRM"' 10CFR50.59 )

level during movement of nonirradiated fuel 1 assemblies within the containment have been i relocated, b

v

l Attachment 7 i

, p CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS v (page 20 of 22) l DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 4.0 DESIGN FEATURES LA3 Details associated with the containment design. UFSAR 10CFR50.59 l Reactor Coolant System desi n. and the meteorological ,

tower location have been re ocated.

LA, Details associated with the fuel assembly design and UFSAR 10CFR50.59 control rod assembly design have been relocated.

l LA3 Details associated with the Exclusion Area Boundary, UFSAR 10CFR50.59 i Low Population Zone, and unrestricted areas and site boundary for radioactive gaseous and liquid effluents have been relocated.

ITS SECTION: 5.0 ADMINISTRATIVE CONTROLS LA Details associated with the minimum requirements for TRM"' 10CFR50.59 shift crew composition have been relocated.

LA, Details associated with functional requirements of UFSAR 10CFR50.54(a) the Independent Safety Engineering Group have been Chapter 17 relocated.

] LA3 The requirements associated with facility staff UFSAR 10CFR50.59 (U training and retraining have been relocated.

LA. The requirements associated with plant review and UFSAR 10CFR50.54(a) l submittal of a reportable event have been relocated. Chapter 17 l LA, The requirerent associated with establishing TRM"' 10CFR50.59 procedures to implement the Process Control Program.

LA. The requirements associated with implementation of UFSAR 10CFR50.54(a) the technical review and control program for Chapter 17 procedure changes have been relocated.

L A, The requirements associated with implementation of TRH"' 10CFR50.59 the in plant radiation monitoring program have been relocated.

LA, The requirements associated with implementation of TRM"' 10CFR50.59 the Offsite Dose Calculation Manual and the radiological environmental monitoring program have been relocated.

LA, The requirement associated with submittal of a report TRM"' 10CFR50.59 to the NRC following specific activity limits being exceeded.

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS v (page 21 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 5.0 ADMINISTRATIVE CONTROLS (continued)

LA g The requirements associated with the retention of UFSAR 10CFR50.54(a) records related to activities affecting quality have Chapter 17 been relocated.

LA n The requirement associated with establishing TRH"' 10CFR50.59 procedures for personnel radiation protection consistent with 10 CFR 20.

LA a Details associated with test and frequency TRM"' 10CFR50.59 requirements for the Control Room Ventilation, the Nonaccessible Area Exhaust Filter Plenum Ventilation, and the fuel Handling Building Exhaust Filter Plenum Ventilation Systems have been relocated.

LA n Details associated with functional requirements of UFSAR 10CFR50.54(a) the Onsite Review and Investigative Function have Chapter 17 been relocated.

LA 3 The requirements associated with containment vessel TRM"' 10CFR50.59 structural integrity have b ~ n relocated.

G LA 3 The requirements associated with diesel fuel oil TRM"' 10CFR50.59 Q testing have been relocated.

LA 3 The requirements associated with component cyclic or TRM"' 10CFR50.59 transient limits have been relocated.

LA g for Byron Station only, the requirements associated TRM"' 10CFR50.59 with ASME Section XI testing requirements have been relocated.

LA a The requirement associated with submittal of a TRM"' 10CFR50.59 startup report to the NRC.

LA n Details associated with the attributes of containment ITS 5.5 n 10CFR50.59 Operability and the requirements associated with Program}6 Appendix J testing of sealing mechanisms for penetrations have been relocated.

LA3 The requirements associated with explosive gas and ITS 5.5 n 10CFR50.59 storage tank radioactivity monitoring have been Program}2 relocated.

LAy Details associated with the pressure and temperature PTLR"' 10CFR50.59 limits. heatup and cooldown rates, reactor vessel material surveillance schedule, and Power Operated Relief Valve lift setpoints have been relocated.

LAn The requirements associated with reactor coolant pump ITS5.5J n 10CFR50 59 flywheel inspections have been relocated. Program g-i L.

Attachment 7 CTS REQUIREMENT RELOCATED TO OTHER LICENSEE CONTROLLED DOCUMENTS

{~

s (page 22 of 22)

DOC ISSUE RELOCATED DOCUMENT CONTROL ITS SECTION: 5.0 ADMINISTRATIVE CONTROLS (continued)

LAn The requirements associated with containment leakage ITS 5.57 10CFR50.59 and air lock testing have been relocated. Program,}6 LA3 The requirements associated with battery inspections ITS 5.S 10CFR50.59 have been relocated. Program,}7 c

LA3 The requirements associated with the responsibility TRM'" 10CFR50.59 of the Shift Engineer for directing the control room command function and the daily operations of the facility have been relocated.

LAy Details associated with establishing and implementing TRM'" 10CFR50.59 procedures to limit the working hours of facility staff who perform safety-related functions have been relocated. l LA, Details associated with plant specific management UFSAR 10CFR50.54(a) position titles have been relocated. Chapter 17 O

lable Notation:

(1) To be incorporated by reference into the UFSAR.

/O V

?'

f O !

l I

i i

i l

ATTACHMENT 8 ENVIRONMENTAL ASSESSMENT I O FOR PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, I

0F FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 i

i i

d i

iO

,-w v, r --r -,.,n -- ~ , , ~ -

ENVIRONMENTAL ASSESSMENT FOR PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSES NPF-37, NPF-66 NPF-72, AND NPF-77 (page 1 of 1)

Commonwealth Edison Company (Comed) has evaluated this proposed license amendment request against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with Title 10. Code of Federal Regulations Part 51. Section 21 (10 CFR 51.21).

Comed has determined that this proposed license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9). This determination is based upon the following:

1. The proposed licensing action involves the issuance of an amendment to a license for a reactor pursuant to 10 CFR 50 which changes a requirement with res)ect to installation or use of a facility component located wit 11n the restricted area, as defined in 10 CFR 20, or which changes an inspection or a surveillance requirement:

2. This roposed license amendment request involves no significant hazards considerations as demonstrated in the enclosure to this letter:

3. There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite: and

4. There is no significant increase in individual or cumulative occupational radiation exposure.

Therefore, pursuant to 10 CFR 51.22(b), neither an environmental impact statement nor an environmental assessment is necessary for this proposed license amendment request.

O w ,Y

ML20133B585

Text

Subject:

References:

Navigation menu

Search