Text

Amends 39,39,26 & 26 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,approving Changes to Tech Spec 3/4.6.3 Re Containment Isolation Valves
	ML20058B291
Person / Time
Site:	Byron, Braidwood
Issue date:	10/17/1990
From:	Barrett R; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20058B296	List: ML20058B291; ML20058B301;
References
	NPF-37-A-039, NPF-66-A-039, NPF-72-A-026, NPF-77-A-026 NUDOCS 9010300081
	Download: ML20058B291 (14)
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-37 1.

TheNuclearRegulatoryCommission(theCommission)hasfoundthat:

A.

The application for amendment by Commonwealth Edison Company (thelicensee)datedApril 20, 1990, complies wit' the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

Thereisreasonableassurance(i)that+.heactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

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

The issuance of this amendment is 'n accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:

9010300001 %0h54 PDR ADOCK pg P

. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 39 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION iY j

Richar/;l / arret't, Director

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Project D rectorate !!!-2 Division of Reactor Projects - Ill, IV, Y and Special Projects l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October li, 1990 l

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UNITED STATES 5 '} e g

NUCLE AR REGULATORY COMMISSION g

WASHINGTON, D C. 20$$b 4.....f

'4 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION UNIT ;" 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-66 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Commonwealth Edison Company (thelicensee)datedApril 20, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.

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

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-66 is hereby amended to read as follows:

b

-2 (2\\ Technical Specifications The re 5nical Specifications contained in Appendix A (NUREG-1113),

as revised through Amendment No. 39 and revised by Attachment 2 to NPF-66 end the Environmental Protection Plan contained in Appendix e,, both of which were attached to License No. NPT-37, dated February 14, 1985 are hereby incorporated into this license. contains a, revision to Appendix A which is hereby incorporated into this license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMIS$10N Richar

$, Director Project [tirectorate 111-2 Division of Reactor Projects - 111, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 17, 1990 i

1

ATTACHMENT TO LitiNSE AMENDMENT NOS. 39 AND 39 l

FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET N05. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Corresponding overleaf pages (indicated by an asterisk) are provided to maintain document completeness.

Remove Pages insert Pages

$3/4 6-17

3/4 6-17 3/4 6-18 3/4 6-18

'3/4 6-23

3/4 6 23 3/4 6-24 3/4 6-24 1

l 1

l

SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-3 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

1 a.

Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position; b.

Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position; and c.

Verifying that on a Containment Vent Isolation test signal, each purge and exhaust isolation valve actuates to its 1 solation position, j

4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to l

Specification 4.0.S.

1 i

1 BYRON - UNITS 1 & 2 3/4 6-17 l

TABLE 3.6-1 CONTAINMENT ISOLATION VALVES i

KAXIMUM PENETRATION VALVE NO.

FUNCTION ISOLATION T7ME (SEC) 1.

Phase "A" Isolation 28 CV8100 RCP Seal Water Returti 10 l

28 CV8112 RCP Seal Water keturn 10 41 CV8152 RCS Letdown 10 r

41 CV8160 RCS Letdown 10 5

WOO 20A Chilled Water 50 l

5 WOOS 6A Chilled Water 50 l

6 W6006A Chilled Water 50 8

WG0208 Chilled Water 50 8

WOOS 6B Chilled Water 50 10 W9006B Chilled Water 50 22 CC9437B*

Excess Ltdn HX Return 10 48 CC9437A*

Excess Ltdn HX Supply 10 i

34 FP010*

Fire Protection 12 l

39 IA065 Instrument Air 15 39 IA066 Instrument Air 15 13 OG079 Hydrogen Recombiner 60 13 OG080 Hydrogen Recombiner 60 13 OG082 Hydrogen Recombiner 60 13 GG084 Hydrogen Recombiner 60 23 OG081 Hydrogen Recombiner 60 23 OG085 Hydrogen Recombiner

-tK) 69 OG057A Hydrogen Recombiner 60 69 OG083 Hyarogen Recombiner 60 56 SA032 Service Air 4.5 56 SA033 Service Air 4.5 80 S00020*

Steam Generator Blowdown 7.5 80-S0005B*

Steam Generator Blowdown 3.0 81 S0002D*

Steam Generator Blowdown 7.5 82 SD002A*

Steam Generator Blowdown 7.5 82 SD005A*

Steam Generator Blowdown 3.0 83 500028*

Steam Generator Blowdown

7. 5 88 SD002E*

Steam Generator Blowdown

7. 5 i

88 S0005C*

Steam Generator Blowdown 3.0 89 SD002F*

Steam Generator Blowdown 7.5 90 SD002G*

Steam Generator Blowdown 7.5 90 500050*

Steam Generator Blowdown 3.0 91 SD002H*

Steam Generator Blowdown

7. 5 BYRON - UNITS 1 & 2 3/4 6-18 AMEN 0 MENT NO. 39

\\

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

_ FUNCTION ISOLATION TIME (SEC) 9.

Manual (Continued) 99 FWO150*,#

Feedwater N.A.

100 FWOISA*,#

Feedwater N.A.

101 FWO15B*,#

Feedwater N.A.

102 FWO15C*,#

Feedwater N.A.

10. Check 28 CV8113 RCP Seal Water Return N. A.

37 CV8348*

RCS Loop Fill N.A.

1 6

W9007A Chilled Water N.A.

10 W9007B 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 CS008A Containment Spray N.A.

16 CS008B Containment Spray N.A.

39

!A091 Instrument Air N. A.

30 WM191 Make-Up Domin N. A.

52 PR032 Process Radiation N.A.

AL PR002G Process Radiation N. A.

AL PR002H Process Radiation N. A.

12 PS231A Hydrogen Monitor N. A.

31 PS2318 Hydrogen Monitor N.A.

27 RY8047 PRT Nitrogen N.A.

44 RY8046 PRT Make-Up N.A.

26 518815*

Safety Injection N.A.

50 SI8818A*

Safety Injection N.A.

50 5188180*

Safety Injection N.A.

51 5188188*

Safety Injection N.A.

51 S18818C*

Safety. Injection N.A.

59

$18905A*

Safety Injection N.A.

59 5189050*

Safety Injection d.A.

l 60 SI8819A*

Safety Injection N.A.

60 SIB 819B*

Safety Injection N. A.

BYRON - UNITS 1 & 2 3/4 6-23 AMEN 0 MENT NO. 21 UA E l GM i

_ TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO.

FUNCTION ISOLATION TIME Q EC)

10. Check (Continued) 60 SI8819C*

Safety Injection N.A.

60 SI8819D*

Safety Injection N.A.

66 SI6841A*

Safety Injaction N.A.

66 SIB 841B*

Safety In.iection N.A.

73 SI89058*

Safety Injection N.A.

73 SI89050*

Safety Injection N. A.

55 S18968 Safety Injection N.A.

l 34 FP345*

Fire Protection N. A.

33 CV8368A*

RCP Seal Injection N. A.

33 CV83680*

RCP Seal Injection N.A.

I 53 CV83688*

RCP Seal Injection N.A.

53 CV8368C*

RCP Seal Injection N.A.

11. S/G Safeties /PORVs 77 MS013D*

Main Steam N.A, 77 MS0140*

ML20058B291

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