ML20085A764

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Proposed Changes to Tech Spec Table 3.7.A,reflecting Correct Valve Positions for Operating Pressure Suppression Head Tank Sys
ML20085A764
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/24/1983
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20085A763 List:
References
NUDOCS 8307070124
Download: ML20085A764 (6)


Text

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ENCLOSURE 1 l PROPOSED TECHNICAL SPECIFICAION REVISIONS TVA BFNP TS 176 SUPPLEMENT 8 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 1

i lDR DD 0 000 P

TA31.E 3.7. A

  • FAI'tARY COWAIWDT ISol.ATION VG 9ES Nu=iber of Power Maximun Action en Operated Valves Operating Normal lettiattog Croup C9tbcard Tine (sec.) Position Signal ._

Valve Identification Inbc :rd

~3 CC 1  % 10 steamitne isolatfor. valves 4 4 3<T<5 0 (FCV-1-14,26,3 7,651 jl-15, 27, 38, & 52) 1 Main steam 1 toe drain isolation 1 1 15 0 CC valves PCV-t-55 & 1-56 SC 1* Reactor Unter sample itne isole- 'l 1 5 C tion valves 4

I$ .

2 RHRS shutdowrt cooling supply isolation valves FCV-74-48 & 47 1 1 40 c SC 2 RalRS - 1.FCI to reactor FCV-74-53, 67 2 30 C SC 2 Reactor vessel head spray isole-tion valves FCi-74-77, 78 . 1 1 30 C SC 2 RHRS flush and drain vent to

  • suppreoston chauber 4 20 C SC FCV-74-102, 103,'119 & 120 2 suppression Chamber Drain 2 15 0(1) GC e FCV 75-57. -58 ~

z 2 Dr79t11 squipe.ent drain discharge $

15 0 GC

, isoletion estves FCV-77-15A, & 15B 2 -

2 Dry.iell floor drata discherse 2 0 g taalattua valves FCV-77-2A & 23 is

  • *These valves isolate only on reactor vessel low low water level (470") and main steam line high radiation of Group 1 isolations.

NOTES

1. These valves are normally open when the pressure suppression head tank is aligned to serve the RHR and CS discharge piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See Specification 3.5.H)

e .

TABLE 3. 7. A FRIPARY CONrAIMHDiT ISotArIOff VALVES Maximus Action on Number of Power 13ormal Init ia t i n4 Operating crerated valves Tame (sec.I Position Signal Inboard Outboard Group Valve Idetification 0 cc 4 4 3<T< 5 1 Itain steamline isolation valves (FCV-1-It, 26, 37, s $1; l-15, 27, 3S & 52)

O CC 1 1 15 1 Main steasta,ne drain isolation

' valves (FCV-1-55 5 1-56) se

  • 5 C 1

1* Reactor water sample line isola- 1 tion valves 2 REAS shutdown cooling supply 1 40 C SC 1

isolation valves (rcv-74-48 s 47) SC J0 C 2

2 RIUt3 - LPCI to reactor .

(rcV-74-53 & 67) 2 Reactor vessel head spray isola- 1 30 c SC 1

tion valves (PCV-74-77 5 76)

N 2 RERS flush and drain vent to 20 c

  • sc 4

y suppression chamber (FCV-74-102, 103, 119, & 120) 2 15 0(1) GC l 2 suppression chamber Crain (FCV-7 5-57 s 58) .

Drywell equipment drain discharge 15 0 cc 2 2 isolation valves (FCV-77-15A & 158) 2 Drywell floce drain discharge 15 0 cc 2

isolation valves (FCV-77-2A 5 25) ligned Notes:

1.

These valves are normally open when the pressure suppression head tank is ad when E y the co to serve the RHR and CS discharge piping and close (See specification 3.5.10 is used to serve the RHR and CS discharge piping. u

  • These valves isolate only on, reactor vessel low low water level.(470") and main steam line high radiation of Croup 1 isolations.

s . .

j . . . ,

a * .

a TAELE 3.7.A PRIMARY CDPTAIIMDiT ImLATICN VALVES 4

Kazimum Actico on

. , Numbe r of Puwe r ograting Normal Ini t i at i g

> operated valves Position Signal Irloard .cutboard Taee (se=.3 ,

Group Valve Identification 0 A' 4 4 3<7<5 1 Main steaaline isolatio.1 valves

( FCV 14, 26, 37, 5 51;  !

1-15, 27, 38 5 52) 15 0 GC 1 1 6 1 Main steamline drain iss14 tion valves (FCV-1-55 6 1-56 C SC

.I 1 5 1* Reactor Water sasple line isola-tion valves 2 RERS shutdown cooling supply 40 C SC 1 1 i solat.aon valves (It'V-74-4 8 s 47) 30 C SC 2

2 RifRS - LPCI t.o reactor (rcy-74-53 6 67) 2 Reactor vessel bead spray isola- ' 30 C SC 1 2 tion valves (FCV-74-77 & 78)

' RERS flush and .irain vent to SC 2 4 20 C U suppression c. baster

" (PcV-74-102, 103, 119, & 120) 2 Suppression Chamber Drain 2 15 0(1) GC (PCV-7 5-57 6 56) .

2 Drywell equipment drair. discharge 2 15 0 GC isolation valves (FCV-17-15A 5 158) 2 Drywell floor drain discharge 15 0 CC 2

isolation valves (FCV-77-2A & 23)

?

c:

z

, 4

~

u n

  • These valves isolate only'on reactor vessel low low water level (470") and main steam li,e high radiation of Group 1 it.olations.

NOTES

1. These valves are normally open when the pressure suppression head tank is aligned to serve the RHR and CS discharg piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See specification 3.5.11)

1 ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION l TVA BFNP TS 176 SUPPLEMENT 8 Description Page 250 (Units 1 and 2)

Page 262 (Unit 3)

For valves FCV 75-57, 75-58, Suppression Chamber drain, it is proposed to change the Normal Position from " closed" to "open" and Action on Initiation Signal from " stays closed" to "goes closed." Also, it is proposed to add the note: "These valves are normally open when the l pressure suppression head tank is aligned to serve the RHR and CS discharge piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See Specification 3 5.H)"

Justification 7

These changes are proposed for clarification of the normal position of the suppression chamber drain valves FCV 75-57 and 75-58. The changes also correct typographical errors in the designation of the suppression chamber drain valves to reflect proper valve numbers and proper action of valves on initiating signal.

These changes reflect the corect valve positions for operating the pressure suppression chamber head tank system. It will not be possible

. to operate the pressure suppression chamber head tank system with the valve alignment shown in the existing technical specifictions. This system was installed and will be used primarily to alleviate certain NRC concerns.

Page 250 for unit 1 includes the changes proposed in TS 176 Supplement 2.

Description and justification for those changes was provided in that submittal.

Page 262 for unit 3 includes the change, proposed in TS 176 Supplement 1, the addition of the footnote on the reactor water sample line isolation valves. ' As explained fully in that submittal the footnote was added to .

- more accurately represent the isolation trips for these valves. f l

Safety Analysis This revision is being made to clarify the normal position of the suppression chamber drain valves FCV 75-57 and 75-58. It does not alter in any way the present method of operation or the overall safety of the i plant. These valves will still go to the safe position in the event of a l containment isolation signal.  !

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ENCLOSURE 3

. BROWNS FERRY NUCLEAR PLANT SIGNIFICANT HAZARDS CONSIDERATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES

1. Does the proposed amendment. jnvolve a significant increase in the probability or consequences of an accident previously evaluated?

No - This revision does not alter in any way the system operation as described in the FSAR.

2. Does the proposed amendment create the proability of a new or different kind of accident from any accident previously evaluated?

No - This revision does not alter in any way the present method of operation or the overall safety of the plant.

3 Does the proposed amendment involve a significant reduction in a margin of safety?

No- This revision does not in any way alter a proscribed margin of safety.

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