ML20134D052

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Proposed Tech Specs Section 3.6.3 Containment Isolation Valves, Being Revised to Support Replacement of Byron & Braidwood Unit 1 Original W Model D4 SGs W/Babcock & Wilcox Intl SGs
ML20134D052
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 01/20/1997
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20134D036 List:
References
NUDOCS 9702040277
Download: ML20134D052 (17)
v • d • e


Text

. . . . _ _ .. _. _ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ - . . _ _ _ _._

I 1 j 7 i 4

I l ATTACHMENT B-1 PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, i

OF FACILITY OPERATING LICENSE  ;

NPF-37 and NPF-66 BYRON NUCLEAR POWER STATION J

l i

Affected Paaes 4

4 1

3/4 6-21 3/4 6-22

3/4 6-23 j 3/4 6-24 l

4 l

I i

4 k

4 s

i w

a f

9702040277 970120 PDR ADOCK 05000454 P PDR <

kWa'byrbwd\stmgenholvalv

~-

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES i

MAXIMUM PENETRATION VALVE NO. FUNCTION ISOLATION TIME ('SEC)

6. Main Steam Isolation (Continued) 85 MS101B* Main Steam 6

'j 86 MS101C* Main Steam 6 (

7. Feedwater Isolation (
76 FWOO9D* Main Feedwater 5 (

76 FWO430*V4 Main Feedwater -

6 j

, 79 FWOO9A* Main Feedwater 5

(

79 FWO43A* M Main Feedwater 6 l /

84 FWOO98* Main Feedwater 5 \

84 FWO43B* M Main Feedwater 6 l 87 FWOO9C* _

Main Feedwater 5 (

87 FWO43C*4% Main Feedwater 6 99 n(f4Wt FWO35D* Main Feedwater 6 99 n $G% *

101swg1R tg FWO358* Main Feedwater 6 101 m ogk u FWO39B*

' Main Feedwater 6 (

10.2=t{awg FWO35C* Main Feedwater 6 i

102g;Wyl)k1x FWO39C* Main Feedwater 6

8. Remote Manual 68 RHS701A*,# RH suction N.A. l 68 RHB701B*,# RH Suction N.A.

75 RH3702A*,# RH Suction N.A.

75 HH8702B*,# RH Suction N.A. 1 59 SI8881* Hot Leg Safety Injection N.A.

73 SI8824* Hot Leg Safety Injection N.A.

SI8825* Hot Leg RH Injection 66 N.A.

60 SIB 823* Cold Leg Safety Injection N.A.

50 SIB 890A* Cold Leg RH Injection N.A. c

. 51 SI8890B* Cold Leg RH Injection N.A.

7 26 SI8843* Cold Leg Safety Injection N.A.

33 CV8355A* RCP Seal Injection N.A.

33 CV8355D* RCP Seal Injection N.A. ,

53 CV83559* RCP Seal injection N.A.

53 CV8355C* RCP Seal Injection N.A.

1 4

BYRON - UNITS 1 & 2 3/4 6-21 -

. _ . _ = _ . . __ .__... _ . ._. - _ . - _ _ _ . . .__.._._ __.__.._._ _ _ . _ _ - ._

l i

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES MAXIMUM i PENETRATION VALVE NO. FUNCTION ISOLATION TIME (SEC)

! 8. Remote Manual (Continued) 59 SI8802A* Not leg Safety Injection N. A.

73 S188028* Hot Leg Safety Injection N.A.

60 SI8835* Hot Leg Safety Injection N.A.

50 SI8809A* RH Cold Leg Injection N.A.

51 5188098* RH Cold Leg Injection N.A.

66 SI8840* Not Leg Safety Injection N.A.

100 Tw(7))p a AF013A* Feedwater N.A.

100 d Qig g AF013E* Feedwater N.A.

101 ,4Q w y AF0138* Feedwater N.A. i 101u *Q1hm .t AF013F" Feedwater N.A.

102a w ub n AF013C* Feedwater N.A.

1021 % ij w AF013G* Feedwater N. A.  !

99 # N ># n AF013D* Feedwater N. A. )

99 x C .t u AF013H* Feedwater N.A.  !

9. Manual j 37 CV8346* RCS Loop Fill N. A. '

I3 VQOl6 Instrument Penetration N.A. 1 I3 VQO17 Instrument Penetration N.A. l I3 VQ018 Instrument Penetration N.A. l I3 VQO19 Instrument Penetration N.A.

15 RYO75 Instrument Penetration N.A.

1 30 WM190 Make-Up Demin N.A. '

57 FC009 Spent Fuel Pool Cleaning N.A.

57 FC010 Spent Fuel Pool Cleaning N.A.

32 FC011 -Spent Fuel Pool Cleaning N.A.

32 FC012 Spent Fuel Pool Cleaning N.A. r 77 MS021D*,# Main Steam . N. A.

78 MS021A*,# Main Staam N.A. i 85 MS0218*,# Main Steam N.A. I 86 MS021C*,# Main Steam N.A.

AL PR002E# Process Radiation N.A. l AL PR033A# Process Radiation N.A.

AL PR033B# Process Radiation N.A.

AL PR002r) Process Radiation N.A.

AL PR033C# , Process Radiation N. A.

AL PR033D# Process Radiation N.A.

8YRON - UNITS 1 & 2 3/4 6-22 .

< , o .

TABLE 3.6-1 (Continued) j CONTAINMENT ISOLATION VALVES s

MAXIMUM PENETRATION VALVE NO. FUNCTION ISOLATION TIME (SEC)

9. Manual (Continued)  :

99 FW0150*,#

100 FWO15A*,#

Feedwaterdeh 0M 6wLLMA N. A.

101 Feedwater3%.Ae. A..mu ;)ng N.A.

j FWO15B*,# Feedwater4 % e m t.. m w a.,)n x N.A.

102 FW015C*,#

Feedwaterggec=_w kuw.gpA N. A.

10. Check i

l 28 CV8113 RCP Seal Water Return N.A.

37 CV8348* RCS Loop Fill N.A.

la 6 W9007A Chilled Water N.A.

10 W90078 Chilled Water N.A.

21 CC9534 RCP Mtr Brng Return N.A.

24 CC9518 RCP Thermal Barrier Return N.A.

! 25 CC9486 RCP Cooling Wtr Supply N.A.

1 1 CS008A Containment Spray N.A.

16 C5008B Containment Spray N.A.

39 IA091 Instrument Air N.A.

4 30 WM191 Make-Up Demin N.A.  !

l 1 52 PR032 Process Radiation N.A. '

i i Al PR002G Process Radiation N.A.

. Al PR002H Process Radiation N.A.

12 PS231A Hydrogen Monitor N.A.

31 PS231B Hydrogen Monitor N.A.

27 RY8047 PRT Nitrogen N.A.

44 RY8046 PRT Make-Up N.A.

1 26 SI8815* Safety Injection N.A.

50 SI8818A* Safety Injection N.A.

50 5188180* Safety Injection N.A.

4 51 SI88188* Safety Injection N.A.

Safety Injection

51 SI8818C* N.A.

SI8905A* Safety Injection 59 N.A. ,

59 SI8905D* Safety Injection N.A. $ 1 60 SI8819A* Safety Injection N.A.  !

60 SI8819B* Safety Injection N.A. I 1

BYRON - UNITS 1 & 2 3/4 6-23 AMENDMENT NO. 21

i i

TABLE 3.6-1 (Continued) 4 CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO. FUNCTION

. ISOLATION TIME (SEC)

10. Check (Continued) i

! 60 SI8819C* Safety Injection i 60 N.A.

SI8819D* Safety Injection N.A.

66 SIB 841A* Safety Injection N.A.

66 SI8841B* Safety Injection N.A.

73 5189058* Safety Injeetion N.A.

73 SI8905C" Safety Injection N.A.

! 55 SI8968 Safety Injection N.A.

3* FP345* Fire Protection N.A.

! 33 CV8368A* RCP Seal Injection N. A.

j 33 CV83680* RCP Seal Injection N.A.

53 CV83688* RCP Seal Injection N.A.

1 53 CV8368C* RCP Seal Injection N. A.

11.,5fGSafeties/PORVs e

77 M5013D* Main Steam N.A.

77 M5014D* Main Stan N.A.

l 77 M5015D* Main 5trAv N.A.

77 MS016D* Main Stve N.A.

! 77 M50170* Main Steam N.A.

78 MS013A* Main Steam N.A.

i 78 M5014A* Main Steam N.A.

I

'/8 M5015A* Main Steam N. A.

) 78 M5016A* Main Steam N.A.

! 78 M5017A* Main Steam N.A.

! 85 M5013B* Main Steam N.A.

! 85 M5014B" Main Staam N.A.

85 M50158* Main Steam N.A.

85 M50168* Main Steam N.A.

85 M5017B* Main Steam N. A.

l S6 M5013C8 Main Steam N.A.

I 86' MS014C* Main Steam N.A.

86 MS015C* Main Steam N.A.

86 M5016C* Main Steam N.A.

86 M5017C* Main Steam N.A.

77 M50180* Main Steam 20 78 MS018A* Main Steam , 20 85 MS0188* Main Steam 20 86 MS018C* Main Staam _ 20 t- n vzt wm a w .: ,

' Rot subject te Type C 1rsakage tests. M.C F _ if:t " '

3 ** Proper valve oparsi. ion will be demonstrated by verifying that the valve (trokes to its required pocition.

l

  1. May be opened :,n an intermittent basis under administrative control.

~_: ..,. ._ s BYRON - UNITS 1 & 2 3/4 6-24 AMENDMENT NO. 39

ATTACHMENT B-2 PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSE l l NPF-72 and NPF-77 BRAIDWOOD NUCLEAR POWER STATION i

i i

Affected Paaes i

3/4 6-21

M 3-22 1

3!d 3-23

, 3/4 6-24 1

I l

kWa'byrbwd'stmgenVsolvaty

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

,i .- - .

J l

j .

i

TABLE 3.6-1 (Continued) .

I I

CONTAINMENT ISOLATION VALVES t l HAXIMUM j PENETRATION VALVE NO. FUNCTION ISOLATION TIME (SEC) j .

s. Main Steam Isolation (Continued) l

! 85 M51018* Main Steam 6 j 86 MS101C* Main Steam 6

7. Feedwater Ison . von

! 76 FWOO90* Main Feedwater 5

76 FWO43D* N Main Feedwater 6 l i

79 FWOO9A* Main Feedwater 5 79 FWO43A* M Main Feedwater 6 i 84 FWOO9B* .

Main Feedwater 5  ! '

i 84 FWO4388 W Main Feedwater 6 Main Feedwater i 87 FW009C* 5 l j 87 ,

FWO43C*s 4 Main.Feedwater 6

99 M hh FWO350* Main Feedwater 6 l 99 we ki,* FWO39D* Main Feedwater 6 l

! 100MG k" FWO39A* Main Feedwater 6  ; i

! 101246T44 FWO358* Main'Feedwater 6 l f 101 W M W W FW039B* Main Feedwater 6 102eMh7P4' FWO35C* Main Feedwater 6 i j 102 t @7Jh6 FWO39C' Main Feedwater 6

8. Remote Manual ,

! 68 RH8701A",# RH Suction N.A.

i 68 RH87018*,# RH Suction N.A.

75 RH8702A*,# RH Suction N.A.

1 75 RH8702B*,# RH Suction N.A.

i 59 SI8881* Hot Leg Safety Injection N.A.

2 73 SI8824" Hot Leg Safety Injection N.A.  :

66 SI8825* Hot Leg RH Injection N.A.

60 SI8823* Cold Leg Safety Injection N.A.  !

50 SI8890A* Cold Leg RH Injection N. A.

51 SI88908" Cold Leg RH Injection N.A.

26 518843* Cold Leg Safety Injection N.A.

33 CV8355A* RCP Seal Injection N.A.  ;

33 CV83550* RCP Seal Injection N.A.  !

53 CV83558* RCP Seal Injection N.A.  ;

53 CV8355C" RCP Seal Injection N. A.

l BRAIDWOOD - UNITS 1 & 2 3/4 6-21 l

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

l

)

i TABLE 3.6-1 (Continued) 4 l

CONTAINMENT ISOLATION VALVES I MAXIMLH PENETRATION VALVE NO. FUNC'. ION ISOLATION TIME (SEC) ,

8. Remote Manual (Continued) 59 SI8802A* Hot Leg Safety Injection N. A.

73 5188028* Hot Leg Safety Injection 60 N.A.

SIPS 35" Hot Leg Safety Injection N.A.

50 SIE909A* RH Cold Leg Injection N. A.

51 SIB 809B* RH Cold Leg Injection 66 N.A.

SI8840* Hot Leg Safety Injection N.A.

100 Agi)(n AF013A* Feedwater N.A.

100es t hit % AF013E8 Feedwater N.A.

1012 q m ,: A AF01388 Feedwater N.A.

101

102 hw7)ns AF013C" Feedwater N.A.

102 :=q n'h AF013G" Feedwater N.A.

99 % p AAw AF013D* Feedwater N.A.

99 4* O p.t x AF013H* Feedwater N.A.

9. Manual 37 CV8346* RCS Loop Fill N. A.

13 VQOl6 Instrument Penetration N.A.

13 VQ017 Instrument Penetration N.A.

13 VQ018 Instrument Penetration N,A.

13 VQO19 Instrument Penetration N.A.

15 RYO75 Instrument Penetration N.A.

30 WM190 Make-Up Domin N.A.

57 FC009 Spent Fuel Pool Cleaning N.A.

57 FC010 Spent Fuel Pool Cleaning N. A.

32 FC011 Spent Fuel Pool Cleaning N.A.

32 FC012 Speat Fuel Pool Cleaning N.A.

77 MS021D*,# Main Steam N.A.

78 M5021A*,# Main Steam N.A.

85 MS021B*,# Main Steam N.A.

86 M5021C*,# Main Steam N.A.

AL PP002E# Process Radiation N.x. I AL Pkd33A# Process Radiation N. A.

AL PR0333# Process Radiation N.A. i AL PR002F# Process Radiation N.A. l AL PR033C# Process Radiation N. A. l AL PR033D# Process Radiation N.A. '

BRAIDWOOD - UNITS 1 & 2 3/4 6-22

.; TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES

. MAXIMUM PENETRATION VALVE NO. FUACTION ISOLATION TIME (SEC)

9. Manual (Continued) 99 FWO15D*,# Fee &ater % E v + _.c.-r. .., ,! u N.A. I 100 FWO15A*,# Feesaterm e - < . . < . . ,t.N.A.

101 FWO15B",# Feedwater - r.re - U - -w- -- aer N.A.

102 FWO15C",# Feedwater u t-.- a e :- ~ a + N.A.

10. Check 1

28 CV8113 RCP Seal Water Return N.A.

37 CV8348" RCS Loop Fill N.A.

6 W6007A Chilled Water N.A.

, 10 W9007B Chilled Water ,

N.A.

1 21 CC9534 RCP'Mtr Brng Return N.A.

. 24 CC9518 RCP Thermal Barrier Return N.A.

25 CC9486 RCP Cooling Wtr Supply N.A.

j 1 CS008A Containment Spray N.A.

, 16 CS008B Containeent Spray N.A.

39 IA091 Instrument Air N.A.

30 WM191 Make-Up Demin N.A.

52 PR032 Process Radiation N.A.

i AL PR002G Process Radiation N.A.  !

AL PR002H Process Radiation N.A.

12 PS231A Hydrogen Monitor N. A.

31 PS231B Hydrogen Monitor N.A.

, 27 RY8047 PRT Nitrogen N.A.

44 RY8046 PRT Make-Up H.A.

26 518815* Safety Injection N.A.

50 SI8818A* Safety Injection N.A.

50 SI88180* Safety Injeetion N.A.

51 SI8818B" Safety Injection N.A.

51 SI8818C* Safety Injection N. A.

59 SIB 905A* Safety Injection N.A.

59 518905D* Safety Injection N.A.

60 SI8819A* Safety Injection N.A.

60 SI8819B* Safety Injection N.A.

BRAIDWOOD - UNITS 1 & 2 3/4 6-23 7 J

a

  • 9 e

s . ,

l

) '

i TA8LE 3.5-1 (Continued) z CONTAINMENT ISOLATION VALVES l

i PENETRATION VALVE NO. MAXIMUM FUNCTION 1

ISOLATION TIME (SEC) l 4

10. Check (Continued)

! 60 SI8819C*

60 Safety Injection N.A.

SIB 819D* Safety Injection 66 SI8841A* N.A.

j 66 Safety Injection N.A.

SI88418* Safety Injection 73 SI89058* N. A.

! 73 Safety Injection N.A.

SI8905C* Safety Injection 55 5I8968 N.A.

34 Safety Infect 1on N. A.

FP345* Fire Protection

} 33 CV8368A* N.A.

33 RCP Seal Injection N.A.

CV83680* RCP Seal Injection

! 53 CV83688* N.A.

j 53 RCP Seal Injection N.A.

CV8368C" RCP Seal Injection 1 N.A.

11. S/G Safeties /PORVs 4

77 MS013D* Main Steam N.A.

l 77 M5014D*

Main Steam N.A.

77 MS015D" Main Steam N.A.

! 77 MS016D*

Main Steam N.A.

77 MS017D* Main Steam N.A.

78 M5013A*

i Main Steam N. A.

78 M5014A* Main Staam 78 MS015A* N.A.

Main Steam N.A.

l 78 MS016A* Main Steam N.A.

78 M5017A* Main Steam 85 M50138* N.A.

Main Staam N.A.

, 85 MS0148* Main Steam i N. A.

85 M50158* Main Steam N.A.

t 85 MS0168* Main 5t?am 85 M5017B* N.A.

i Main Steam N.A.

86 M5013C* Main 5 team N.A.

{ 86 MS014C*

- Main Steam N.A.

i 86 MS015C* Main Steam N.A.

} 86- MS016C* Main Steam

' 86 MS017C* N.A.

Main Steam N.A.

77 MS0180* Main Steam 78 MS018A*

20 Main Steam 20 85 MS0188* Main Steam 20 86 MS018C* Main Steam _ _ _ - ___ 20 f k x t e ,;a. _,% rc w.w. ~'

"Not subject to Type C leakage tests N t i Ii'I '

    • Proper valve operation will be demonstrated by ve_rifying that tL valve

< strokes to its required position,  !

fMay be opened on an intermittant basis under adeinistrative control.

t m c. , , y . , . -(.. ...c ae.. w..

< 8RAIDWOOD - UNITS 1 & 2 3/4 6-24 AMENDMENT NO. 26 j

_ _ - . .t

1 ATTACHMENT C i EVALUATION OF  !

SIGNIFICANT HAZARDS CONSIDERATIONS l FOR PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFIC-ATIONS, OF FACILITY OPERATING LICENSES i NPF-37, NPF-66, NPF-72 AND NPF-77 i i

Commonwealth Edison Company (Comed) has evaluated this proposed amendment and has i

determined that it involves no significant hazards considerations. According to Title 10, Code ,

of Federal Regulations, Section 50, Subsection 92, Paragraph c (10 CFR 50.92 (c)), a i proposed amendment to an operating license involves no significant hazards considerations if j operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability ce consequences of an accident previously evaluated; or
2. Create the possibility of a new or different kind of accident from any accident previously evaluated, or
3. Involve a significant reduction in margin of safety.

A. INTRODUCTION As a result of the planned replacement of the Westinghouse D4 steam generators at Byron Unit 1 and Braidwood Unit 1, changes will be made to the containment isolation piping arrangements at the penetrations associated with the Feedwater (FW) and Auxiliary Feedwater (AF) systems. As a result of these changes, there will be no split FW flow with the replacement steam generators. AF flow will be fed into the main FW piping outside of containment and the existing FW tempering penetration will be used for a new steam generator recirculation sv.ch to be used during periods of extended shutdown. Additionally, since the replacemerc ..om generators use a feedring design rather than a preheater design, the FW lsolation Bypass line and associated containment isolation valves will no longer be required. Table 3.6-1 of the Technical Specifications (TS) must be updated to reflect these changes. These changes do not affect the containment isolation capability originally designed to the criteria in 10 CFR 50, Appendix A, General Design Criteria (GDC) 54 through 57 as reflected in the Byron /Braidwood Updated Final Safety Analysis Report (UFSAR).

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. 1 i

l B. NO SIGNIFICANT HAZARDS ANALYSIS

1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

, Technical Specification 3/4.6.3 establishes the operability requirements for containment isolation valves as required by the Byron and Braidwood Operating  !

Licenses in compliance with Genera! Design Criteria 54 through 57 of Appendix A to 10 CFR 50. The operability of the containment isolation valves ensure that the  ;

containment atmosphere will be isolated from the outside environment in the event '

of a release of radioactive material to the containment atmosphere. Table 3.6-1 identifies these isolation valves and captures relevant information to ensure these valves remain operable under required conditions.

These proposed changes result in the elimination of the FW lsolation Bypass isolation valves. These isolation valves are not required with the replacement steam l generator design. The remaining isolation valves have not been altered in any way, j only the piping associated with them has been altered to the revised configuration.  !

These changes do not result in alteration of any containment penetrations.

Failure of the piping between the isolation valve and the containment penet. ration is l considered as an accident initiator. However, all piping changes between the I isolation valve and the containment penetrations meet the requirements of the original design.

Therefore, since all original piping design criteria are met and the actual number of containment isolation valves is reduced, the proposed change does not involve a significant increase in the probability of an accident previously evaluated.

Each penetration identified in the proposed change is associated with a closed system inside containment and, as such, is provided containment isolation in accordance with the applicable requirements of GDC 54 through 57. There are four analyzed transients which take credit for feedwater isolation and are, therefore, relevant to this proposed change. These accidents are: 1) feedwater system malfunctions that result in an increase in FW flow,2) inadvertent opening of a stear,1 generator relief or safety valve,3) steam cystem piping failure, and 4) FW system pipe break. All operability requirements for the affected containment isolation valves are unaffected by this proposed change.

The containment isolation valves' functions, system operating conditions, and accident responses are unchanged as a result of the new configuration. Therefore, since all original design criteria are met and each remaining isolation valve continues to provide the same degree of containment isolation as the original design, the proposed change does not involve a significant increase in the consequences of an accident previously evaluated.

kWabyrbwdttmgenVsolvalv j l

j

2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

All modifications associated with the proposed changes will be outside of containment and can be characterized as the rearrangement of piping systems. All piping changes will comply with the original design of the plant and will retain required containment isolation capabilities per the requirements of GDC 54 through 57 as required by the current design basis. Piping configurations within the area of the containment penetration and the containment isolation valves are required to minimize branch connections per guidance in the Standard Review Plan (SRP)

Section 3.6.2.

Therefore, since there are no unique configurations or reductions in design requirements, thi., proposed change does not create the possibility of any new or different kinds of accidents from those previously evaluated.

3. The proposed change does not involve a significant reduction in a margin of safety. i l

The proposed changes to the containment isolation arrangement are being made j consistent with the same codes, standards, and isolation criteria as are currently in l use at Byron and Braidwood. The containment isolation valves remaining in place following the steam generator replacement are unchanged with regard to tneir function, capability, reliability, or physical requirements. Containment isolation capability in accordance with GDC 54 through 57 is maintained at current levels of protection for the health and safety of the general public. Therefore, this proposed l change does not involve a significant reduction in the margin of safety.

Based on the above, Commonwealth Edison has concluded that these changes involve no significant hazards considerations.

kWabyrbwc"stmgenksoh<alv

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

,< *s . .

ATTACHMENT D ENVIRONMENTAL ASSESSMENT FOR PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS 'F j FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 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, 2

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 i determination is based upon the following:

1. The proposed licensing action involves the issuance of an amendment to a l license for a reactor pursuant to 10 CFR 50 which changes a requirement with ,

respect to installation or use of a fau?ty component located within the restricted 1 area, as defined in 10 CFR 20, or which changes an inspection or a surveillance l requirement. This proposed license amendment request will allow Comed to I delete four feedwater bypass valves, change the containment penetrations ]

associated with eight feedwater valves, change the containment penetrations associated with eight auxiliary feedwater valves, and change the function of four j feedwater valves to a steam generator recirculation function. All of these changes affect only Unit 1 at Byron and Braidwood; )

2. this proposed license amendment request involves ne significant hazards considerations;
3. there is no significant change in the types or significant increase in the amounts of any effident that may be released offsite; and
4. there is no significant increase in individual or cumulative occupational radiation exposure.

l 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.

kWatyrtud'stmgenh'valv

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ATTACHMENT E l 1

)

FIGURE 1: EXISTING ISOLATION ARRANGEMENT

\

FIGURE 2: REVISED ISOLATION ARRANGEMENT (UNITS 1 ONLY) l I

l 1

1 l

1 l

l 1

l l

l i

kvita'byrbwdstmgenVsolvatv

62mmical Feed) .

FWotsA typions ser

O FWD 158, C, D CONTAINMENT H MTL8-

. __g)--. (Assenry ru---- --)

i eso tyyloal'-J i em AF0138, C, D, F, G, H

! 4 (AscearyFeedweser)

?

?

FWO36A C, D l P100  ; (FeedwaterTemportrq$

s=

GENERATOR 4

l lm0 AOfs typices for A i b FWO30A FWO308, C. D

! Ho typicallor

! - FWD 006, C, D l P 79 DAG (Main FM i lYP P87 i

i

)haFWO43A FWO438. typical for C. D (Feedwaterleolmson Bypass) W SD002C,E,G P 82 (SG Blowdown) l l j PUa,P88 P90 Aofs typtest for

SD0028 SD002D F.L'

,I P 83

.l (SG Blowdown) i esi.Pse.P91 NOTE: Schematic representation only; l intermediate valves not shown j i

i i

CONTAINMENT FIGURE 1 1 EXISTING ISOLATION ARRANGEMENT

- . _ . , .. . . .m . _ . ..._._ . ._ . _ . . _ . _ . .

s W F**d)

W- ww __m _

CONTAINMENT FWO158, C, D 7 g i

i

=

apossa W*

AF0138, C, D, F, G, H i 4 WFeedweser) l l

% WaEc.u t

l Pico faf __ Tempering)

STEM  !

l Q gar.Pso GENERATOR  ! WC'I b AC/S W'ud W A O' O

, n .

! rwoosa I

P 79 i W (Mah Foodweser)

YPEPer i

e i  !

l iOS WW i SD002A S00ttc, E. G l P82 k (SG fit 9wdown) j l Y P E P90 Y/ l

= --

800028 SD002D F.H

+

i l P 83 I M (SG Dbedown) j , YP .P91 NOTE: Schematic representation only; intermediate valves not shown j

==

h**  :

s i

i; 7-CONTAINMENT Wet Layup l System Additions ,

' ~~~ ~~

, FIGURE 2 ,

REVISED ISOLATION ARRANGEMENT

, (UNITS 1 ONLY)

- - - - ~

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