Text

Amends 66 & 92 to Licenses DPR-71 & DPR-62,respectively, Modifying Tech Specs to Provide Clarification of Primary Containment Integrity Requirements & Editorial &/Or Administrative Corrections
	ML20087P108
Person / Time
Site:	Brunswick
Issue date:	03/06/1984
From:	Vassallo D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20087P109	List: ML20087P108; ML20087P111;
References
	DPR-62-A-092, DPR-71-A-066 NUDOCS 8404060058
	Download: ML20087P108 (36)
	v • d • e

_

Q REQ

/

e UNITED STATES 8.

', ^

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 F

,J CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-71 1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee) dated September 7, 1982 complies with 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 confornity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the 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 in accordance with 10 CFR Part 51-of the Commission's regulations and all applicable reouirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71-is hereby amended to read as~follows:

8404060056 840306 PDR ADOCK 05000324 P

PDR

1

. ' 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as.

revised through Amendment No. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Chances to the Technical Specifications Date of Issuance: March 6, 1984

.t

,1 ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:

Remove Insert 3/4 3-48 3/4 3-48 3/4 3-49 3/4 3-49 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 4-4 3/4 4-4 3/4 6-17 3/4 6-17 3/4 7-14 3/4 7-14 3/4 7-16 3/4 7-16 3/4 7-18 3/4 7-18 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-23 3/4 7-23 3/4 7-25 3/4 7-25:

3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 J

(BSEP-1-19) m TABLE 3.3.5.2-1

=

REMOTE SHUTDOWN MONIT0ilIN" INSTRUMENTATION R

MINIMUM READOUT CHANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBER LOCATION OPERABLE a

H'

l. Reactor Vessel Pressure RSP*

1 (C32-PI-3332 and C32-PT-3332)

2. Reactor Vessel Water Level RSP*

1 (821-LT-N017D-3, B21-LSH-N017D-3)

(B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A)

3. Suppression Chamber Water Level RSP*

I (CAC-LI-3342 and CAC-LT-3342) d' y

4. Suppression Chamber Water Temperature RSP*

1 (CAC-TR-778-7)

5. Drywell Pressure RSP*

1 (CAC-PI-3341 and CAC-PT-3341)

6. Drywell Temperature RSP*

1 (CAC-TR-778-1,3,4)

7. Residual Heat Removal Head Spray RSP*

1 Flow (E11-FT-3339 and Ell-FI-3339)

8. Residual Heat Removal System Flow RSP*

1 (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338) m 5.

9. Residual Heat Removal Service Water RSP*

1 S

Discharge' Differential Pressure

.z (Ell-PDT-N002BX and Ell-PDI-3344) g C Remote Shutdown Panel, Reactor Building 20' Elevation

(BSEP-1-19)

E TABLE 4.3.5.2-1

.E I- $

REMOTE SHUTDOWN MONITORIhG INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL CHANNEL FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION zy

1. Reactor Vessel Pressure M

Q (C32-PI-3332 and C32-PT-3332)

~

2. Reactor Vessel Water Level (B21-LT-N017D-3, B21-LSH-N017D-3)

NA Q

(B21-LI-3331, B21-LI-R604AX, B21-LT-3331, M

Q B21-LT-N026A)

3. Suppression Chamber Water Level M

R (CAC-LI-3342 and CAC-LT-3342) 4.' Suppression Chamber Water Temperature M

R y

(CAC-TR-778-7) s-

5. Drywell Pressure (CAC-PI-3341 and CAC-PT-3341)

M Q

6. Drywell Temperature-(CAC-TR-778-1,3,4)

M R

7. Residual Heat Removal Head Spray Flow (Ell-FT-3339 and Ell-FI-3339)

M Q

8. Residual Heat Removal System Flow-M Q

(Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)

9. Residual Heat Removal Service Water Discharge M

Q

$I Differential Pressure (Ell-PDT-N002BX k.

and Ell-PDI-3344) a

.if

( BSEP--l-19)

,a TABLE 3.3.5.7-1 FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE FLAME HEAT SMOKE 1.

Reactor Building #1 Zone 1

-17' O

O 1

Zone 2

-17' 0

0 1

Zone 3

-17' O

O 6

Zone 4

-17 0

0 6

Zone 5 20' 0

0 12 Zone 6 20' O

O 11 Zone 7 20' 0

0 10 Zone 8 50' 0

0 11 Zone 9 50' 0

0 15 Zone 10 80' 0

0 8

Zone 11 80' O

O 10 Zone 12 98' O

0 3

Zone 13 117' 0

0 1

Zone 14 117' 0

0 34 Zone 16 77' 0

0 4

2.

Control Building Zone 1 70' 0

0 9

Zone 2 49' O

O 4

Zone 3 49' 0

0 4

Zone 4 49' 0

0 13 Zone 5 49' 0

0 14 Zone 6

-49' 0

0 6

Zone 7 23' 0

0 3

Zone 8 23' 0

0 3

Zone 9 23' 0

0 25 Zone 10 23'

'O O

24 Zone 11 23' O

0 3

Zone 12 23' 0

0 3

Zone 13 49' 0

0 9

Zone 14 49' 0

0 9

Zone 15 70' 0

l' 0

Zone 16 70' 0 0 3.

Diesel Generator Building Zone 1 2'

O O

25 Zone 2 2'

0' 0

24 Zone 3 50' 0

0 9

Zone 4 23' 0

0 7-Zone 5 23' 0

0 5

Zone 6 23' 0

0 5

l BRUNSWICK - UNIT 1

-3/4 3 Amendment No. 66

(BSEP-1-19) e i

TABLE 3.3.5.7-1 (Continued)

INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE FLAME HEAT SMOKE 3.

Diesel Generator Building (Cont'd)

Zone 7 23' 0

0 5

Zone 8 23' 0

0 5

Zone 9 23' O

O 8

Zone 10 50' 0

0 9

4.

Service Water Building Zone 1 4'

0 0

7 Zone 2 20' O

O 6

5.

A0G Building Zone 1 20' O

O 2

Zone 2 20' O

O 2

Zone 3 20' 1

5 1

Zone 4 37' - 49' 1

6 6

BRUNSWICK - UNIT 1 3/4 3-61.

Amendinent No. 66

(BSEP-1-19) e t

REACTOR COOLANT SYSTEM i

3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of all reactor coolant system safety / relief valves shall be OPERABLE with lif t settings within t 1% of the following values.*#

4 Safety-relief valves @ 1105 psig.

4 Safety-relief valves @ 1115 psig.

3 Safety-relief valves @ 1125 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the safety valve function of one safety / relief valve inoperchle, a.

restore the inoperable safety valve function of the valve to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the safety valve function of two safety / relief valves inoperable, restore the inoperable safety valve function of at least one of the valves to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i c.

With the safety valve function of more than two safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2 The safety valve function of each of the above required safety / relief valves shall be demonstrated OPERABLE ~ in accordance with the Surveillance Requirements of Specification 4.0.5.

The lift setting pressure shall correspond to ambient conditions of the valves at normal operating temperature and pressure.

BRUNSWICK - UNIT 1 3/4 4-4 Amendment No. 66-

(BSEP-1-19)

~_

-E TABLE 3.6.3-1 (Continued)

E

{:

PRIMARY CONTAINMENT ISOLATION VALVES n*

ISOLATION TIME 1!

(Seconds)

VALVE FUNCTION VALVE GROUP E

l

'N Reactor vessel head spray isolation valves 8

30 r

E11-F022 E11-F023 RHR shutdown cooling supply isolation valves 8

30 Ell-F008 EIl-F009 RHR injection isolation valves 8

30 El1-F015A, B R

l o

RHR discharge isolation valves to radwaste 2

30 El1-F040 py Ell-F049 i

RHR process sampling valves 2

30 Ell-F079A, B Ell-F080A, B I

E f.'

NOTE 1:

See Specification 3.3.2, Table-3.3.2-1 for isolation signal that operates each valve group.

5'

.F

_- _ - _ _ _ ~

(BSEP-1-19)

TABLE 3.7.5-1 (Continued)

E SAFETY-RELATED HYDRAULIC SNUBBERS *

' SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HICll RADIATION ESPECIALLY DIFFICULT NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE 2f 5

Instrument Sensing System w

1B21-70lSS164 Drywell 104' I

No No 70lSS167 104' I

No No 70lSS169 100' I

No No 70lSS170 103' I

No No 70lSS171 99' I

No No 70lSS172 101' I

No No 701SS175 100' I

No No 70lSS177.

94' I

No No

~

70lSS178 97' I

No No R

70lSS179 96' I

No No 70lSS184 88' I

No No u.

h Reactor Closed Cooling Water System 1RCC-32SS30 Reactor Building 55' A

No No 32SS45 60' A

No No 36SS78 54' A

No.

No i

37SS79 54' A

No No 39SS80 59' A

No No 38SS81 54'-

A No No 7Ssi12 57' A

No No 48SS167 59' A

No No 48SS168-58' A

No No

~48SS169 60'

.A.

No No 50SS272 4'

A No No

(

60SS121 Drywell-17' I

No No g

60SS122 16' I

No No m

65SS128

'7' I

No No 65SS129 9'.

I No No

,f 71SS139 9'

I No No 73SS145 S'

I No No 19sS157 21' I

No No 19SS160 29' I

No No

(BSEP-1-19)

TABLE 3.7.5-1 (Continued) l SAFETY-RELATED IlYDRAULIC SNUBBERS

2:

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT h

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE 8

Reactor Core Isolation Cooling System E

lE51'-4SS45 Drywell 31' I

No No E

3SS46-39' I

No No 3SS47 39' I

No No 4SS66 39' I

No No 4SS68 40' I

No No 4SS69 40' I

No No 4SS70 39' I

No No 4SS71 36' I

No No 4SS72 31' I

No No 4SS73 30' I

No No 41SS51 Reactor Building 40' A

No No u

42SS74 20' A

No No 5

42SS75 20' A

No No w

42SS76 18' A

No No

.b 42SS77 5'

A No No 42SS78 0'

A No No 42SS79 4'

A No No 42SS80

-13' A

No No 42SS81

-16' A

No No 42SS82

-9' A

No No 40SS83

-9' A

No No 40SS84

-9' A

No No 40SS85

'-12' A

No No 40SSb6

-9' A

No No 40SS87

-15' A

No No 40SS88

-13' A

No No

.f.

'41SS89

.41' A

No No c

41SS95

-41' A

No No k

19SSI13

-17' A

No No 19SSI14

-16' A

No No g_'

49SS129 0'

A No No l

r

l (BSEP-1-19)

TABLE 3.7.5-1 (Continued)

SAFETY-RELATED llYDRAULIC SNUBBERS

E g.

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT o

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE M.

8 Nuclear Steam Vent System E'

.Q IB21-44SS129 Drywell 104' I

No No 44SS131 93' I

No No 44SS134 99' I

No No 44SS136 97' I

No No 44SS137 96' I

No No 44SS138' 95' I

No No 44SS141 87' I

No No 44SS142 87' I

No No 44SS143 87' I

No No 44SS146 87' I

No No 46SS147 82' I

No No l

u3 44SS149 85' I

No No 44SS150 83' I

No No y

.L 147SS155 75' I

No No 47SS156 78' I

No No

'47SS157 75' I

No No Standby Liquid Control System IC41-9SS4 Drywell 63' I

No No 9SS5 47' I

No No 9SS8 42' I

-No No 9SS10

'38' I

No No 9SS11 39' I

No No 9SS12 69' I

No No i

9SS 13 -

52' I

No No 9SS26 Reactor Building 72' A

No No 9SS27.

72' A-No No 6SS34 84' A

No No n

O.

(BSEP-1-19)

TABLE 3.7.5-1 (Continued) l~

SAFETY-RELATED HYDRAULIC SNUBBERS *

a E

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT l

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE Fuel Fool Cooling System E

E IG41-ISS22-Reactor Building 12' A

No No ISS24 38' A

No No ISS30 38' A

No No 12SS32 9'

A No No 12SS33-9' A

No No 15SS37 111' A

No No 20SS76 108' A

No No

-19SS79 89' A

No No l

22SS85 108'

-A No No 12SS98

'88' A

No No w'

.6SSI11 88' A

No No S

7SS121' 87' A

No No y.

SSS152 82' A

No No

[

Reactor Recirculation System IB32-SSAl Drywell 8'

I No No

~

SSBl 81'

'I No No SSA2 1l

I No No SSB2 1l' -

I No No SSA3 1l' I

No No SSB3-1l' I

No No SSA4' 21' I

No No

.SSB4 21'-

I No No SSA5 21' I

No No

.I SSB5 21' I

No No S'

SSA6 27

I No No k---

SSB6-27' I

No No c-SSB9A 30' I

No No SSB98 30' I

No No

.f~

.SSA10

.24' I

No No 3

+

~.

3'

}

h

+f s

t (BSEP-1-19) s 3

.^

TABLE 3.7.5-1 (Continued)

, ;' { "

j SAFETY-RELATED llYDRAULIC SNUBBERS *

-i SNUBBER p SYSTEM SNUBBER INSTALLED ACCESSIBLE OR.

HIGH RADIATION ESPECIALLY DIFFICULT

+,,

NO.

' ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** I

'TO' REMOVE 1

.g g

Reactor Recirculation System (Continued)

~*E_

SSAll Drywell (Cont'd) 11' I

No No g

y.

SSBil 11' I

No No SSAl2A 30' I

No No SSA12B 30' I

No j>

g No SSB12A 30' I

No No SSB12B 30' I

No

,' i, j

No Reactor Vessel Instrumentation

\\

j IPS-3554

.Drywell 32' I

No No 3558 32' I

No '

,' )

No

(

3561-32' I

No,,

No

);

3562 60' I

' No,l,

i No t'

?'3567 63' I

No N -

No e

i,3570 32' I

No No 3

7.

36i3 32' I'

No No

.G 3617A 32' I

No No 36178 32' I

No No r

3751 34' I

No No 3752 34' I

No No Reactor'Feedwater System IB21-2SS3 Drywell 38' I

No No 2SS4 56' I

No No 3SS6 41' I

No No

'3SS9 39' I

No No 3SSil 41' I

No No 3SS12 40' I

No No

'3SS13 61' I

No No g

e SSS17 38' I

No No E.

SSS18 56' I

No No

}.

E.

.!?

(BSEP-1-19)

TABLE 3.7.5-1 (Continusd) h SAFETY-PELATED HYDRAULIC SNUBBERS

z k'

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT Q

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE I

i Reactor Feedwater System (Continued) c 6SS20 Drywell (Cont'd) 41' I

No No H

6SS23 39' I

No No P

6SS25 41' I

No No 6SS26 40' I

No No 6SS27 63' I

No No ISS227 34' I

No No ISS228 38' I

No No 2SS229 53' I

No No l

-2SS230 62' I

No No 3SS231 40' I

No No 3SS232 36' I

No No R

3SS233-40' I

No No 3SS234 48' I

No No y

3SS235 63' I

No No g-4SS236 34' I

No No 4SS237 38' I

No No SSS238 53' I

No No

.5SS239 61' I

No No 6SS240 41' I

No N(,

6SS241.

36' I

No No 6SS242 39' I

No No 6SS243

.48' I.

Na No 6SS244 61' I

No No Residual Heat Removal System lEll-90SS267 Drywell 79' I

No No 90SS268 86' I

No No f

90SS271 86'

.I No No g,

90SS274 93' I

No No g

90SS275 93' I

No No g

90SS277 96' I

No No 90SS278 96' I

No No 2

,0 90SS280 101'-

I No No g

_90SS281 93'.

I No No 90SS282 101' I

No No w

(BSEP-1-19)

TABLE 3.7.5-1 (Continued)

SAFETY-RELATED HYDRAULIC SNUBBERS

m

. 'N SNUBBER'.

SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT N

NO.

-ON.

LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE

_?.

c Residual Heat Removal System (Continued) d IEll-132SS264 Reactor BIdg.

31' A

No No 21SS296 (Cont'd) 39' A

No No 2ISS297 39' A

No No 47SS323 42' A

No No 47SS326 42' A

No No 47SS328 42' A

No No 49SS330 42' A

No No 49SS331 42' A

No No 49SS333.

42' A

No No 49SS334 43' A

No No 49SS336 40' A

No No M

128SS355 42' A

No No 49SS359 42' A

No No E

127SS376 59' A

No No U

128SS387 43' A

No No 2SS396

.S' A

No No 2SS397.

3' A

No No SSS398

-41' A

No No 2SS399

-3' A

No No SSS400

-3' A

No No 4SS401

-12' A

No No SSS402

-12' A

No No 3SS403

-11'

-A No No 6SS404

-12' A

No No 8SS405.

-14' A

No No

-g' 6SS406

-14' A

No No g

-8SS407

-15' A

No No g

12SS408

-14' A

No No g

116SS409:

-9' A

No No 113SS410

-9' A

No No y

9SS411

-14' A

No No 109SS412

-14' A

No No

.2SS413 0'

A No No 132SS414 43' A

No No

(BSEP-1-19)

TABLE 3.7.5-1 (Continued) h SAFETY-RELATED HYDRAULIC SNUBBERS

g g

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT g

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE Residual Heat Removal System (Continued) 2

-lEl1-89SS460 Reactor Bldg.

10' A

No No E

89SS461 (cont'd) 6' A

No No H

53SS462 15' A

No No 53SS463 14' A

No No 53SS464-14' A

No No 53SS465 14' A

No No 53SS466 14' A

No No 50SS467

.14' A

No No 50SS468 17' A

No No 18SS469 53' A

No No 18SS470 43' A

No No R

89SS480 67' A

No No 89SS487 67' A

No No

.y 89SS489 67' A

No No g-89sS491 67' A

No No 91SS499 69' A

No No 91SS500 57' A

No No 56SS504 14' A

No No 56SS505 7'

.A No No 56SS506 3'

A No No 56SS507 3'-

A No No "56SS508 4'

A-No No

_46SS509 8'

A No ho 246SS510 11' A

No No 4

46SS511 10' A

No No 46SS512

-l' A

No No

- k 58SS514' 14' A

No No g,.-

'_49SS 515 37' A

No No a

s 49SS516 37' A

No No

.h 56SS517

-5' A

No No l

SISS546 32' A

No No

._ 2

o' 51SS547 28' A

No No

,g 115SS549 31' A

No No

(BSEP-1-19)

TABLE 3.7.5-1 (Continued)

E SAFETY-RELATED HYDRAULIC SNUBBERS

E k

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE g

Residual Heat Removal System (Continued) 2: '

IEll-54SS551 Reactor Bldg.

31' A

No No U

54SS552 (Cont'd) 28' A

No No H

98SS554 32' A

No No 58SS563 7'

A No No 58SS565 13' A

No No 58SS566 6'

A No No 107SS573 15' A

No No 69SS574 6'

A No No 91SS575 53' A

No No 68SS577 8'

A No No 53SS596 14' A

No No y

50SS597 26' A

No No

~

y Service Water System y

ISW-133SS22 Reactor Building

-6' A

No No 110SS35

-5' A

No No 174SS70 42'

.A No No 173SS72 14' A

No No 142SS74 40' A

No No 142SS75 40' A

No No 142SS82 70' A

No No l

140SS86 45' A

No No 153SS102 44' A

No No 173SSI10 48' A

No No 173SS114 70' A

No No

-103SSil7 41' A

No No k

103SS121 38' A

No No g

103SS126 60' A

No No j

103SS127

'57' A

No No

.R

!?

(BSEP-1-19)

TABLE 3.7.5-1 (Continued)

+

h.

SAFETY-RELATED HYDRAULIC SNUBBERS

z h

. SNUBBER SYSTEM SNUBBER. INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

.p NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE I

Service Water System (Continued) ez E

ISW-106SS131 Reactor BIdg..

60' A

No No 100SS145 (Cont'd).

59' A

No No 100SS149 60' A

No No 106SS151 59' A

No No 106SS156 60' A

No No 142SS163 60' A

No No

142SS164 8'

A No No

.142SS165-8' A

No No 175SS166A-

'42' A

No No 175SS166B

'42' A

No No 4

140SS167 42' A

No No 142SS168 58' A

No No y

142SS169 71' A

No No g

,174SS174

.42' A

No No l

173SS175 30' A

No No

.133SS177

-5' A

No No 100SS193 62' A

'No No 106SS211 60' A

No No l

106SS212 60' A

No

' No -

.106SS213 59' A

No No

'106SS214-60'-

A No No 127SS215~

17' A

No No 123SS216

.17' A

No No

.H:

g.

.y

[$8 KEG %,,

UNITED STATES

-[I

'g NUCLEAR REGULATORY COMMISSION

.j WASHINGTON, D. C. 20555

%; ~ ~ /

CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No. 92 1

License No. DPR-62 1.

The Nuclear Regulatory Comission. (the Comission) has 'found ~ that:

A.

The application for amendment by Carolina Power & Light' Company (the licensee) dated September 7, 1982 complies with the standards and requirements'of the Atomic Energy Act of 1954, as amended (the Ac2) and the Comission's rules and. regulations ' set forth in 10 CFR Chapter I; i

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 comon defense and security or to the health 'and safety of the -

public; and i

E.

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

2.

Accordingly,:the license 1.s amended-by changes to the'.Tehhnical; Specifications as indicated in the attachment to this' license amendment, and paragraph 2.C.(2) of Facility Operating' License No. DPR-62 is hereby amended to read as follows:

v w

ey 5-y--

wefr m-t

, 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 6, 1984 i

-.... ~

ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-62 i

DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:

Remove-Insert 3/4 3-48 3/4 3-48 3/4 3-49 3/4 3-49 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 4-4 3/4 4-4 3/4 6-17 3/4 6-17 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7-19

.3/4 7-19 3/4 7-22 3/4 7-22 3/4 7-28 3/4 7-28 3/4 7 3/4 7-30 3/4 7-31' 3/4 7-31 3/4 7-33 3/4 7-33 f

n

(BSEP-2-19)

TABLE 3.3.5.2-1 E~

REMOTE SHUTDOWN MONITORING INSTRUMENTATION

-E

~

E MINIMUM 5

READOUT CHANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBER LOCATION OPERABLE E-

.1.

Reactor Vessel Pressure RSP*

1 O

(C32-PI-3332 and C32-PT-3332) ra

2. Reactor Vessel Water Level RSP*

1 (B21-LT-N017D-3, B21-LSH-N017D-3)

(B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A)

3. Suppression Chamber Water Level RSP*

1 (CAC-LI-3342 and CAC-LT-3342)

.4. Suppression Chamber Water Temperature RSP*

1

.g (CAC-TR-778-7) s~

y

5. Drywell Pressure RSP*

1

'g (CAC-PI-3341 and CAC-PT-3341)

6. Drywell Temperature RSP*

1 (CAC-TR-778-1,3,4)

7. Drywell Oxygen Concentration Local Panel 1

(CAC-AT-1259-2).

8. Residual. Heat Removal. Head Spray RSP*

1

-Flow (Ell-FT-3339 and Ell-FI-3339)

9. Residual Heat Removal System Flow RSP*

1

.g-(Ell-FT-3338, Ell-FI-3338,..and Ell-FY-3338)

RSP*

1

10. Residual Heat Removal Service Water c-Discharge Differential Pressure.

(El1-PDT-N002BX and El1-PDI-3344)

.O

.h

Remote Shutdown. Panel, Reactor Building 20' Elevation

(BS"P.2-19)

TABLE 4.3.5.2-1 h

REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

. $i

c CHANNEL CHANNEL

~ FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION l.

Reactor Vessel Pressure M

Q h

(C32-PI-3332 and C32-PT-3332) a N

2.

Reactor Vessel Water Level (B21-LT-N017D-3, B21-LSH-N017D-3)

NA Q

(B21-LI-3331, B21-LI-R604AX, B21-LT-3331, M

Q B21-LT-N026A) 3.

Suppression Chamber Water Level M

R (CAC-LI-3342 and CAC-LT-3342)

.4.

Suppression Chamber Water Temperature M

R (CAC-TR-778-7)

S.

Drywell Pressure (CAC-PI-3341 and CAC-PT-3341)

M Q

~S 6'.

Drywell Temperature (CAC-TR-778-1,3,4)

M R

7.

Drywell Oxygen Concentration (CAC-AT-1259-2)

M Q

8.

Residual Heat Removal Head Spray Flow (Ell-FT-3339 and Ell-FI-3339)

M Q

9.

Residual Heat Removal System Flow (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)

M Q

10.. Residual Heat Removal Service Water Discharge M

Q Differential Pressure (El1-PDT-NCO2BX and Ell-PDI-3344) e an h

(BSEP-2--19)

TABLE 3.3.5.7-1 FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE FLAME HEAT SMOKE 1.

Reactor Building #2 Zone 1

-17' 0

0 1

Zone 2

-17' 0

0 1

Zone 3

-17' 0

0 6

Zone 4

-17' 0

0 6

Zone 5 20' 0

0 12 Zone 6 20' 0

0 10 Zone 7 20' 0

0 9

Zone 8 50' 0

0 11 Zone 9 50' 0

0 15 Zone 10 80' 0

0 9

Zone 11 80' 0

0 10 Zone 12 98' O

O 3

Zone 13 117' 0

0 1

Zone 14 117' 0

0 34 Zone 16 77' 0

0 4

2.

Control Building Zone 1 70' 0

0.

9 Zone 2 49' O

0 4

Zone 3 49' 0

0 4

i Zone 4 49' 0

0 13 Zone 5 49' 0

0 14 Zone 6 49' 0

0 6

Zone 7 23' 0

0 3

s Zone 8 23' 0

0 3

Zone 9 23' 0

0 25 Zone 10 23' O

0 24 Zone 11 23' 0

0 3

Zone 12 23' 0

0 3

Zone 13 49' 0

0 9

Zone 14 49' O

O 9

Zone 15 70' O

1 0

Zone 16 70' 0

1 0

3.

Diesel Generator Building Zone 1 2'

0 0

'25 Zone 2 2'

0 0

24 Zone 3 50' 0

0 9

Zone 4 23' 0

0 7

Zone 5 23' 0

0 5

Zone 6 23' 0

0 5

GRUNSWICK - UNIT 2 3/4 3-60 Amendment No. 92

(BSEP-2-19) 1 TABLE 3.3.5.7-1 (Continued) 1 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE FLAME HEAT SMOKE 3.

Diesel Generator B.tilding (Cont'd)

Zone 7 23' 0

0 5

Zone 8 23' 0

0 5

Zone 9 23' 0

0 8

Zone 10 50' 0

0 9

4.

Service Water Building Zone 1 4'

0 0

7 Zone 2 20' O

O 6

5.

A0G Building Zone 1 20' O

O 2

Zone 2 20' 0

0 2

Zone 3 20' 1

5 1

Zone 4 37' - 49' 1

5 6

2 e

T l

- BRUNSWICK - UNIT 2-

'3/4 3-61

' Amendment No.92 -

(BSEP-2-19)

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of all reactor coolant system safety / relief valves shall be OPERABLE with lif t settings within t 1% of the following values.*

4 Safety-relief valves @ 1105 psig.

4 Safety-relief valves @ 1115 psig.

3 Safety-relief valves @ 1125 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the safety valve function of one safety / relief valve inoperable, a.

restore the inoperable safety valve function of the valve to OPERABLE l

status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the safety valve function of two safety / relief valves inoperable, restore the inoperable safety valve function of at least one of the valves to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With the safety valve function of more than two safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2 The safety valve function of each of the above required safety / relief valves shall be demonstrated OPERABLE in accordance with the Surveillance Requirements of Specification 4.0.5.

j

The lift setting pressure shall correspond to ambient conditions of the valves at normal operating temperature and pressure.

' BRUNSWICK - UNIT 2 3/4 4-4 Amendment No.92

(BSEP-2-19)

TABLE 3.6.3-1 (Continued)

N PRIMARY CONTAINMENT ISOLATION VALVES E

N ISOLATION TIME I!

VALVE FUNCTION VALVE GROUP (Seconds) c Reactor vessel head spray isolation. valves 8

30 H

Ell-F022 N-Ell-F023 RHR shutdown cooling supply isolation valves 8

30 Ell-F008 F11-F009

'RHR injection isolation valves 8

30 Ell-F015A, B l

RHR discharge isolation valves to radwaste 2

30 Sg Ell-F040 8'

Ell-F049 cn l

[;

RHR process sampling. valves 2

30 Ell-F079A, B Ell-F080A, B NOTE 1:

See Specification 3.3.2, Table.3.3.2-1 for isolation signal that operates each valve group.

g.

.an i8

(BSEP-2-19),

TABLE 3.7.5-1 SAFETY-RELATED liYDRAULIC SNUBBERS *

~

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT i '

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE

'E Core Spray System s

2E21-2SS32 Reactor Building 66' A

No No 25SS91

-6' A

No No l

2SS16 0'

A No No 2SS17 13' A

No No 15SS19

-3' A

No No 15SS20

-3' A

No No 28SS23

-4' A

No No 25SS96

-6' A

No No 40SS106

-12' A

No No 40SS107

-12' A

No No 39SS108

-12' A

No No

.y 39SS109-

-12' A

No No 2SS31 68' A

No No Y

'6SS41 70' A

No No U

6SS42 69' A

No No 2SS18 14' A

No No' 2E21-3SS46 Drywell-63' I

No No 3SS47 63' I

No No 3SS48' 65' I

No No 3SS49 66' I

No No 7SS53 63' I

No No 7SS54 63' I

No No 7sS55 65' I

No No 7SS56

-66' I

No No ii.

E

.if 4

(BSEP-2-19)

TABLE 3.7.5-1 (Continued) en

~l SAFETY-RELATED HYDRAULIC SNUBBERS

s SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

~S NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE 5

Reactor Water Cleanup System y

.2G31-ISS3' Drywell 54' I

No No l

Condensate Drains System 2B21-51SS103 Drywell 29' I

No No 51SS105 26' I

No No 51SS106 18' I

No No 50SS109 31' I

No No 50SS111 28' I

No No

'5ISSI13' 23' I

No No 51SS115 24' I

No No 51SSil8 24' I

No No f

High Pressure Coolant Injection System

[

2E41-4SS44 Drywell 40' I

No No' N

4SS45.

35' I

No No 4SS47.

40' I

No No 4SS49 37' I

No No

.4SS50 40' I

No No 4SS51 30' I

No No

.gg I

lif k

(BSEP-2-19)

TABLE 3.7.5-1 (Continued) m g

SAFETY-RELATED HYDRAULIC SNUBBERS

v>

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT -

Q NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE i

Nuclear Steam Vent System 2821-44SS129 Drywell 104' I

No No H

44SS131 93' I

No No N

44SS134 99' I

No No 44SS136 97' I

No No 44SS137 96' I

No No 44SS138 95' I

No No 44SS141 87' I

No No 44SS142 87' I

No No 44SS143 87' I

No No 44SS146 87' I

No No 46SS147 82' I

No No 44SS149 85' I

No No R

44SS150 83' I

No No 47SS155 75' I

No No y

47SS156 78' I

No No y

47SS157' 75' I

No No Standby Liquid Control System 2C41-9SS4_

_Drywell 63' I

No No l

9SSS 47' I

No No

~9SS8 42' I

No No

'9SS10 38' I

No No

-9SS11 39' I

No No 9sS12

'69' I

No No 9SS13 52' I

No No 2C41-9SS26 Reactor Building 72' A

No No k

9sS27 72' A

No No

.R 6SS34

.84' A

No No

?e R

!?h

A.

a,b

,~+ -

w

-4 a.

-w (BSEP-2-19)

TABLE 3.7.5-1 (Continusd)

E SAFETY-RELATED HYDRAULIC SNUBBERS

s SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT.

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE' Reactor Feedwater System i

E 2B21-2SS3 Drywell~

38' I

No No N

2SS4 56' I

No No 3SS6 41' I

No No 3SS9 39' I

No No 3SSil 41' I

No No 3SS12 40' I

No No

-3SS13 61' I

No No SSS17.

38' I

No No SSS18 56' I

No No 6SS20 41' I

No No 6SS23 39' I

No No R

6SS25-41' I

No No 6SS26 40' I

No No y

6SS27 63' I

No No ISS227 34' I

No No ISS228 38' -

I No No 2SS229 53' I

No No 2SS230 62'-

I No No I

a itA

.F 1

4 a

(BSEP-2-19)

TABLE 3.7.5-1 (Continued)

'E SAFETY-RELATED HYDRAULIC SNUBBERS

E E

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGH RADIATION ESPECIALLY DIFFICULT.

5 NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE M

Residual Heat Removal System (Continuel)

'E E 2 Ell-60SS440 Reactor Bldg. (Cont'd) 13' A

No No w

65SS441 3'

A No No 65SS442 3'

A No No 60SS443 11' A

No No 73SS444 2'

A No No 21SS445 5'

A No No 68SS448 13' A

No No 75SS449 2'

A No No 61SS450 7'

A No No 60SS451 13' A

No No 60SS452 13' A

No No (a

60SS453 10' A

No No S

60SS454 10' A

No No u

89SS459 11' A

No No b

89SS460 10' A

No No 89SS461 6'

A No No 53SS462 15' A

No No 53SS463 14' A

No No

-53SS464 14' A-No No 53SS465 14' A

No No 53SS466 14' A

No No 50SS467 14' A

No No 50SS468 17' A

No No 56SS504 14' A

No No 56SS505 7'

A No No 56SS506 3'

A No No

(

56SS507 3'

A No No o

56SS508 4'

A No No I

46SS509' 8'

A No No

k 46SS510 1l' A

No No

^$.

(BSEP-2-19)

TABLE 3.7.5-1 (Continued)

E SAFETY-RELATED liYDRAULIC SNUBBERS

E E

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGli RADIATION ESPECIALLY DIFFICULT.

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE Service Water Systern E

U 2SW-133SS22 Reactor Building

-6' A

No No w

110SS35

-5' A

No No 173SS72 14' A

No No 142SS164 8'

A No No 142SS165 8'

A No No 133SS176 14' A

No No 133SS177

-5' A

No No 142SS74 40' A

No No 142SS75 40' A

No No 140SS86 45' A

No No l

153SS102 44' A

No No R

153SS109 44' A

No No 173SS110 48' A

No No y;

153SSil5 44' A

No No

' g 103SS121 38' A

No No 42' A

No No 140SS167 173SS175 30' A

No No 142SS82 70' A

No No 173SSI14 70' A

No No 103SS126 60' A

No No N.

g-

an 18

.(BSEP-2-19)

TABLE 3.7.5-1 (Continued) g SAFETY-RELATED HYDRAULIC SNUBBERS

E y

SNUBBER SYSTEM-SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT.

g NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE

.M 1

8 Service Water System (Continued)

E

.p 2SW-103SS127 Reactor BIdg. (Cont'd) 57' A

No No 106SS 131.-

60' A

No No n

100SS145 59' A

No No 100SS149 60' A

No No 106SS151 59' A

No No 174SS70 42' A

No No 106SS156 60' A-No No 142SS168 58' A

No No 142SS169 71' A

No No 100SS193 62' A

No No l

106SS211 60' A

No No 106SS212 60' A

No No T

106SS213 59' A.

No No

.y -

106SS214 60' A

No No 6

103SSil7 41' A

No No 142SS163.

O A

No No 175SS166A 42' A

No No 175SS1668 42' A

No No 109SS173 14' A

No No 174SS174 43' A

No No i

2

.e a, -

(BSEP-2-19)

TABLE 3.7.5-1 (Continued)

SAFETY-RELATED flYDRAULIC SNUBBERS *

-e E

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGil RADIATION ESPECIALLY DIFFICULT N

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE P:

Steam Relief Discharge System (Continued) e-Q 2B21-33SS251 DryweII (Cont'd) 32' I

No No w

20SS256 44' I

No No l

20SS257 37' I

No No 20SS258 36' I

No No 20SS260 18' I

No No 20SS261 20' I

No No 20SS262 15' I

No No 27SS264 10' I

No No

~ 27SS266 17' I

No No 27SS267 18' I

No No

=27SS269 36' I

No No u

27SS270 44' I

No No 3

27SS272 42' I

No No u

-58SS275 18' I

No No da 58SS276 30' I

No No 58SS277' 31' I

No No

.58SS279 36' I

No No 58SS280 37' I

No No 58SS281 38' I

No No 12SS286 39' I

No No 12SS287 39' I.

No No 12SS288 44' I

No No 12SS289 39' I

No No 12SS290 43' I

No No 12SS292 42' I

No No 34SS296 35' I

No No 34SS297 35' I

No No

-34SS298 44' I

No No I

34SS299 39' I

No No 34SS300 44' I

No No

'E i

..

ML20087P108

Text

Attachment:

Attachment:

Navigation menu

Search