ML20034B953

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Proposed Tech Specs,Revising Pages 3/4 3-25,3/4 3-26, 3/4 3-27,3/4 3-28 & 3/4 6-19a Re Containment Isolation Valve
ML20034B953
Person / Time
Site: Beaver Valley
Issue date: 04/23/1990
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20034B949 List:
References
NUDOCS 9005010210
Download: ML20034B953 (44)
v • d • e


Text

__

~

e -

q 4-hTTACHMEliT A-1 Revise the-Beaver Valley Unit ~No.

1 _ Technical-Specifications as follows:-

Remove Paces

-Insert Paaes 3/4.3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 6-19a

.3/4 6-19a-3/4 6-19k 3/4 6-19b 3/4 6-19c 3/4 6-19c 3/4 6-19d 3/4 6-19d l

3/4 6-19e 3/4 6-19e i

3/4 6-19f

_3/4 6-19f 3/4 6-19g 3/4 6-19g 3/4 6-19h 3/4 6-19h 3/4 6-191 3/4 6-191.

3/4 6-19j 3/4 6-19j 3/4 6-19k 3/4 6-19k 3/4 6-22 3/4 6-22 3

3/4 6-25

\\

B3/4 6-3 B3/4 6-3 i

l i

i gg0 10 900423 P

(CK 03o99334 PDC d

'\\

TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTIQH RESPONSE TIME IN SECONDS i

l' l.

Manual a.

Safety Injection (ECCS)

Not Applicable i

Feedwater Isolation Not Applicable l

L Reactor Trip (SI)

Not Applicable Containment Isolation-Phase "A"

Not Applicable Containment Vent and Purge Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Rx Plant River water System Not Applicable b.

Containment Quench Spray Pumps Not Applicable Containment Quench Spray Valves Not Applicable Containment Isolation-Phase "B"-

Not Applicable l

c.

Containment Isolation-Phase "A"

Not Applicable d.

Control Room Ventilation Isolation Not Applicable l

2.

Containment Pressure-Hiah a.

Safety Injection (ECCS) 5 27.0*

b.

Reactor Trip (from SI) 3.0 c.

Feedwater Isolation 5 13.0(1) l d.

Containment Isolation-Phase "A"

5 22.0(3)/33.0(2) e.

Auxiliary Feedwater Pumps Not Applicable f.

Rx Plant River Water System 5 77.0(3)/110.0(2)

DEAVER VALLEY - UNIT 1 3/4 3-25 PROPOSED

-4 1

TABLE 3.3-5 (Continued)__

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 2.

Containment Pressure-Low-a.

Safety Injection (ECCS)

$ 27.0*/27.0#

b.

Reactor Trip (from SI) 3.0 c.

Feedwater Isolation 5 13.0(1) l d.

Containment Isolation-Phase "A"

$ 22.0(3) c.

Auxiliary Feedwater Pumps Not Applicable f.

Rx Plant River Water System 1 77.0(3)/110.0(2) l l

BEAVER VALLEY - UNIT 1 3/4 3-26 PROPOSED

t 3

TABLE 303-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS f

L 2.

Sigan Line Pressure-Low a.

Safety Injection (ECCS)

$ 77.0#/37.0##

b.

Reactor Trip (from SI)

S 3.0 c.

Feedwater Isolation s 13.0(1) l d.

Containment Isolation-Phase "A"

$ 22.0(3)/33.0(2).

q e.

Auxiliary Feedwater_ Pumps Not Applicable f.

Rx Plant River Water System

$ 77.0(3)/110.0(2) g.

Steam Line Isolation S

8.0 5.

Containment Pressure--Hiah-Hich a.

Containment Qu9nch Spray

$ 85.0(2) b.

Containment Isolation-Phase (B)

Not Applicable c.

Control Room Ventilation Isolation S 22.0(3)/77.0(2)-

6.

Steam Generator Water Level--Hiah-Hiah a.

Turbine Trip-Reactor Trip 2.5 (Above P-9)

I b.

Feedwater Isolation 5 13.0(1) l 7.

Containment PressyP,_e--Intermediate Hich-High a.

Steam Line Isolation

-8. 0 8.

Steam 11ne Pressure Rate--Hich Necative a.

Steamline-Isolation s

8.0 i

9.

Loss of Power a.

4.16kV Emergency Bus Undervoltage 1.3 (Loss of Voltage) b.

4.16kV and 480v Emargency Bus 5 95 Undervoltage (Degraded Voltage)

BEAVER VALLEY - UNIT 1 3/4 3-27 PROPOSED

L y'

6

. TABLE 3.3-5 (Continu-d)-

j

l 1

TABLE NOTATION I

Diesel generator starting and sequence loading delays included.

Response

time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps and Low Head Safety Injection pumps.

Sequential.

transfer of charging pump suction-from the volume control-tank 1

(VCT) to the., refueling water storage tank (RWST valves open, then VCT valves close) is not included.

Diesel generator. starting and sequence' loading delays D21 l

included.

Offsite power available.-

Response

time limit includes opening of. valves to establish SI path and attainment.

of discharge pressure for centrifugal charging pumps.

Sequential transfer of charging pump suction from the volume control tank (VCT) to the refueling water storage tank (RWST)

(RWST valves open, then VCT valves close)- is included.

Diesel generator starting and sequence ~ loading delays included..

Response-time limit includes opening of valves to establish ~SI path and attainment of discharge pressure for centrifugal charging pumps.

Sequential transfer of charging pump suction I

from the volume control tank (VCT).-

to-the refueling water i

storage tank (RWST) (RWST valves open, then VCT valves close).is included.

F l

(1)

Feedwater system.

overall response time shall

include verification of valve regulating and bypass valves. stroke times applicable to the feedwaterl (2)

Diesel generator starting and sequence loading. delays included.

(3)

Diesel generator starting and sequence. loading delays ngt included.

4 BEAVER VALLEY - UNIT 1 3/4 3-28 PROPOSED

TABIE 306-1 ONIADMENT PDEIRATIONS

+

MAXIN M MAXDUE PENT IN3IDE:

SIPOR:

._O_UISI E SIROEE NO.-AREA IDENTIFICATICN/mmON VALVE TIME

  • fSEC)

VAIRE TDE*f M w

1-D OCR to RHS Hz 1A & RHS 'Punp 1A Seal Cooler (1)M N-10C-112A2 N/A (1)1Cm-247 -

N/A E

i 5

2-D Cm frun RHS Hx IB & REE Punp 1B Seal Cooler (1)MN-10C-112B3 N/A (1)10 3 -252 N/A f

3 Spare l

O 4-D Om to BfE Hx 1A & RHS Rap 1A Seal Oooler (1)MN-10C-112A3 N/A (1)10 2 -251 N/A e

h 5-D OCR frun RHS HK 1B & RHS Punp 1B Seal Cooler (1)M N-10C-112B2 N/A (1)10CR-248 N/A 6-B Spare mu 7-A High Head SI to Hot legs (3) (2)1SI-83 N/A (3) (2)MN-ISI-869A N/A

.l 5z~

t 3m 8-C OCR to RCP 1B & 1C 'Lhel'nal Barriers (B)W-10C-107D1 20 (B)W-10C-107D2 20

$1

  • f 9-B CCR frun Shruxi Coolers (B)W-10C-111D1 20 (B)W-10C-111rn 20 10-B Spare 11-B Air Recirc. Cooling WateIH3ut (B)W-10C-110D -

30 (B)W-10C-110F2 30 (B)W-10C-110F1 30 12-A Spare 13-D Deluge Systen to OMT Hose Reels 1FP-827 N/A (A)W-1EP-107 N/A l

14-D Air Recirc. Cooling water-In (B)W-10C-110E3 30 (B)W-10C-110E2 30 15-A Coolant Systen Charging (3)(2)101-31 N/A (2) (2)MN-101-289 -

15

.l 16-B CCR to Shroud Coolers (B)W-10C-111A2

~20 (B)W-10C-111A1 20 c

. -.. = _ _, = _ _ -..

TABIE 3.6-1 Caf1AIf5ENT PDEIRATIGES

+

2 E 'd 2

1& M IPEIIE SM OUISIIE SINEE NJ.-AREA IDENTIFICATIN/-nN VALVE TDE* (SEK3 VAWE TDE*(SEC) 17-A CCR to RCP 1B (B)W-10C-103B1 20 (B)W-10C-103B 20 5

18-A CXR to RCP 1C (B)W-10C-103C1 20 (B)W-100-103C 20 I

19-A RCP'o Seal Water Return (A)MN-10f-378 15 (A)MW-10f-381 15

{

10f-369 N/A w

20-C SI Acx:um. Makeup ISI-42 N/A (1)1SI-41 N/A p

g i

21-B Spare 22-B Spare u

w.:

oo 23-B Spare oe EO 24-SgD RHS to RHST 1REI-14 N/A 1Ril-15 N/A 1Rif-16 N/A 25-B CCR frtat RCP 1B & 1C IOturm (B)TV-10C-105D1 20 (B)W-1CC-105D2 20 26-C 001 frtan RCP 1A 'Ihermal Barrier (B)W-10C-107El 10 (B)TV-10C-107E2 10 27-C CIR frtan RCP 1A Motor (B)W-10C-105El 14 (B)TV-1CC-10SE2 14 28-A RCS Istdown (A)W-iOI-200A 7.5 (A)TV-101-204 7.5

'(A)W-10f-2 COB 7.5 (A)TV-101-200C 7.5 (1)MN-101-142 N/A RV-101-203.

N/A 29-A Primary Drain Transfer Pung #1 Disdarge (A)TV-1DG-108A 5

(A)'IV-1DG-108B 5

30-B Spare 31-D Deluge Systen to Cable FEim:uation Area 1FP-804 N/A (A)'IV-1EP-105 N/A l

^

-., ~ ~.,.

TABIE 3.6-1 cntrAINMENT PDT2mATIONS i

Mnx1Mun Mngan PDir INSHE STROKE OUEEDE SD UKE NO.-AREA IDENTIFICATIN/msdumm VALVE TIME *(SEC)

VALVE TIME

  • fSBC) 32-C Deluge System to RHR Area 1FP-800 N/A (A)TV-1FP-106 N/A 33-C High Head SI to Hot Legs (3) (2)1SI-84 N/A (3) (2)MN-ISI-869B

~N/A i

l 34-A Spare y

35-A Seal Injection Water RCP 1A (10) (2)1m-181 N/A (3) (2)MN-1m-308A N/A x

l g

36-A Seal Injection Water RCP 1B (10)(2)101-182 N/A (3) (2)MW-1m-308B N/A l

37-A Seal Injection Water RCP 1C (10) (2)1m-183 N/A (3) (2)MN-1G-308C N/A 38-A Containnent Sunp Punp Discharge

. (A)TI-1DA-100A 10 (A)TI-IIR-100B 10 39-C Steam Generator IA Blowdown Closed System N/A (3) (2) (A)TV-11D-100A 20 ist' g*

40-A Steam Generator 1B Bloktbwn Closed System N/A (3) (2) (A)W-IID-1008 20 8T Steam Generator 1C Blowdown Closed Systen N/A (3) (2) (A)TV-IID-100C 20 g g 41-B 42-C Cwh Air to Fuel Handling ISA-15 N/A ISA-14

.N/A Erniirwaarit 43-B Air Activity MtnitorKXIt (A)1V-1CV-102-1 5

(A)T7-1CV-102 5

44-B Air Activity Monitor-In (A)TV-1CV-101A 5

(A)TV-1CV-101B 5

45-B Primary grade Water to PRP IBC-72 N/A (A)TV-1RC-519

,12 i

46-A diarging Fill Header (10) (2)1m-170 N/A' (3) (2) (1)PCV-1m-160 N/A l

47-B Instrument Air llIA-91 N/A IIA-90 N/A.

-.. ~

.~

'IABLE 3.6-1 cmrADDDTP PIEBATIONS MAXInun nexpor PDFr INSIN S'IRNE WTSHE SIBW E NO.-AREA IDDFTIFICATIN/mmN VALVE TDE* fSEC)

VAIFE TDE*(SEC)

E 48-B Primary Vent Header (A)W-1DG-109A2 5

(A)W-1DG-109Al 5

49-C Nib.uf:n Supply to PRP 1RC-68 N/A (A)W-1RC-101 5-50-C Spare C*

51-C Spare EF R

52-C Spare

~

53-C Nib.uf:n Supply to SI Am=ilators (A)W-ISI-101-2 5

(A)W-1SI-101-1 5

54-B Spare 55-1-A SI W=ilator Suple (A)W-ISS-109Al 20 (A)W-ISS-109A2 20 55-2-A Otfr Isakage Monitoring Open Tape (A)W-11M-100A1 5

8T (A)W-11M-100A2 5

0%

55-3-A Spare

.I 55-4-A PRP Gas Sanple (A)W-1SS-111A1 20 (A)W-1SS-111A2 20

)

56-1-A Pressurizer liquid Suple (A)W-ISS-100A1 20 (A)W-ISS-100A2 20 j

56-2-A RCS Cold Ieg Suple (A)W-ISS-102A1 20 (A)W-ISS-102A2 20 56-3-A RCS Cold leg Suple (A)W-ISS-105A1 20 (A)W-ISS-105A2

20 56-4-A SIM GEN 1A Blowdown Sanple

. Closed System N/A (3) (2) (A)W-ISS-117A 20 -

l l

57-1-A Ceff Isakage Monitoring Open Taps (A)W-11M-100A1 5

(A)W-11M-100A2 5

i

TAB T 3.6-1 03rIADGBFr Fr.ru::mATIGIS Maxatu Moans PDTP INSIIE SDUE:

OIRSHE S'DRDBE NO.-AREA HDTTIFICATImhm.aumm VALVE TIME *(SED VAINE TIME *fSgu.

57-2-A OMP Isakage Monitorirg Open Taps (A)W-11M-100A1 5

g (A)W-11M-100A2 5

57-3-A Spare 2

l-'

57-4-A Spare 4

58-B CCR to RCP 1A (B)W-10C-103Al 20 (B)W-10C-103A 20 e

?

59-C Spare so-SgD Iow Head SI to Hot Iegs (3) (2)1SI-13 N/A

. (3) (2)MmT-ISI-890A N/A mu (3) (2)1SI-451 N/A E3

'N/A (3) (2)lDT-ISI-890C

. N/A g,

61-SgD Low Head SI to Cold legs (3) (2)1SI-10 N/

. (3) (2)1SI-11 N/A o;f (3) (2)1SI-12 N/A 62-SgD Low Head SI to Hot legs (3) (2)1SI-14 N/A (3) (2)lDT-ISI-890B N/A (3) (2)1SI-452 N/A 63-SgD QSP Disdarge 360* Header 1QS-4 N/A.

(B)fDT-1QS-101B 75(4).

64-SgD QSP Discharge 360* Header 1QS-3 N/A (B)MDV-1QS-101A 75(4).

65 Fuel Transfer 'Ibbe (7) Flange N/A (2) (6)HI-1 N/A l j

66-SgD Outside RSP 2A Suction frce O MP (B) (2)lDT-1RS-155A 75(4):

67-SgD Outside RSP 2B Suction frota OMP (B) (2)lDT-1RS-155B

- 75(4) 68-SgD Low Head SI Punp 1A Suction froun OMr Simp

. (3) (9) (2)lpf-ISI-860A N/A l

69-SgD Iow Head SI Pung 1B Suction fran OMP Sunp (3) (9) (2)lD7-ISI-860B N/A

- 1

...._.v4.

.--w

~

m

.,g.w

,. q p y

.~

d -

r

" - -. + +

"*e-e*W

TABE 3.6-1 mNTAINMENP WNEmATIONS Pax 1Mtw smxnts PENP INSIN S1BCEE (MSIE Sm0EE NO.-AREA IIENTIFICEPIONnmaum0N VAWE TIME

  • pr)

VA WE TDE* U:5r) 70-SgD Outside RSP 2B Discharge IRS-101 N/A (B) (2)fDV-1RS-156B 75(4)-

m

.i 71-SgD Outside RSP 2A Discharge IRS-100 N/A (B) (2)IOV-1RS-156A 75(4)

[

72-SgD Spare 73-SgD Main Steam Icop 1A Bypass Closed Systemi N/A (1) (2)PDV-IIE-101A N/A' c

Main Steam RHR Valve Closed Systen N/A (1) (2) (6)HCV-IDE-104 N/A.

i P.

Main Steam Icop 1A Closed Systen N/A

- (2)W-IPE-101A 5

i Main Steam Line Drain Closed Systen N/A (2)W-1BE-111A 8

l Main Steam to hwiliary Feed Rap C1ceed Systen N/A (2)f0V-196-105 N/A j

Main Steam AN,;&ic Duap Closed Systen N/A (2) (6)PCV-IDE-101A N/A Main Steam Safety Valves Closed Systen N/A (2)(6) Safety Valves N/A' mu i

83 3 e.

74-SgD Main Steam Icop 1B Bypass Closed Systen N/A (1) (2)IOV-1pE-101B N/A i

N.'.

Main Steam RHR Valve Closed Systen N/A.

(1) (2) (6)HCV-1PE-104 N/A Main Steam Icop 1B Closed Systen N/A (2)W-1MS-101B 5

l Main Steam Line Drain Closed Systen N/A-(2)W-1BE-111B 8

l Main Steam to Awiliary Feed Rap Closed Systen

.N/A (2)fDV-IIE-105 N/A 4

. Main Steam AN,;&ic Dunp Closed Systen N/A (2) (6)PCV-1MS-101B N/A l

Main Steam Safety valves Closed System N/A (2)(6) Safety Valves N/A I

75-SgD Main Steam Icop 1C Bypass Closed Systen N/A (1) (2)lDV-IIE-101C N/A

. Main Steam RHR Valve Closed Systen N/A-(1) (2) (6)HCV-1fE-104 N/A Main Steam Icop 1C Closed Systen N/A

_ 2)W-1pE-101C 5-(

Main Steam Line Drain Closed Systemt N/A (2)W-IPE-111C

'8 I

Main Steam to hwiliary Feed Rap Closed Systen N/A (2)fDV-196-105 N/A Main Steam A N,; H ic Dtap

- Closed System N/A

- (2) (6)PCV-11E-101C N/A

)

j Main Steam Safety Valves

' Closed Systen N/A (2)(6) Safety Valves.

N/A '

l 76-SgD FW Icop 1A Closed Systen N/A.

' (2)DOV-1FW-156A N/A AFW Icop 1A -

Closed Systen iN/A (2)1FW-42 N/A y

77-SgD FW Iocp 1B Closed Systen N/A (2)l0V-1FW-156B N/A AEW Icop 1B Closed System N/A (2)1FW-43' N/A q

d

___,~

.m

TABIE 3.6-1 00NIATNMENT PINEIPATIONS MAXDEM MAXD52f PENP INSIIE SIROE :

CUISIIE SD0tE; NO.-AREA INNPIFICATICNnma2umCN VALVE TIME *(SEC)

VALVE TDE* fSEK3 g

78-SgD N Iocp 1C Closed System N/A (2)MN-1N-156C N/A g

AN Icop 1C Closed System N/A.

(2)1N-44 N/A e

79-SgD RW to IA RSP Hx Closed Systen N/A (2)MN-1RN-104A N/A o

{

80-SgD RN to 1C RSP Hx Closed System N/A (2)MN-1RN-104C N/A 1

M 5

c 81-SgD RN to 1B RSP Hx Closed System N/A (2)MN-1RN-194B N/A 5

82-SgD RW to 1D RSP Hx Closed System N/A (2)MN-1RN-104D N/A 83-SgD RN from 1A RSP Hx Closed System N/A (2)MN-1RN-105A N/A

- i l

{

84-SgD RW fran 1C RSP Hx Closed System N/A (2)MN-1RN-105C N/A h[

85-SgD RN frun IB RSP Hx Closed System N/A (2)MN-1RN-105B N/A'

' eo" 86-SgD RW from 1D RSP Hx Closed System N/A.

(2)MN-1RN-105D N/A 87-SgD H2 Discharge to O@ff N/A 1HY-111 N/A IHY-197 N/A 88-SgD H2 Discharge to Offf N/A 1HY-110 N/A 1HY-196 N/A

^

i 89-SgD Main Condenser Ejector Vent.

1AS-278 N/A (B)TV-1SV-100A 20-i i

90-SgD 09fP Purge Exhaust VS-D-5-3B

- (11) (5)8 VS-D-5-3A (11) (5)8 I

91-SgD Offf Purge Supply VS-D-5-5B -

(11)(5)11 VS-D-5-5A (11) (5)8

)

l VS-D-5-6 (5) N/A i

4

,.%,a c

-% r1 t-y

.m h

't

-e--ir+4-w-y 7

m

-nwa

- g7

.y-

-pnar#g

'IABLE 3.6-1 CINEAl!@ENT PljNSIPATIONS MAXPOf MAXDUf PIwr INSEE SIBDEE OUISIIE SIROEE lo.-AREA IDENPIFICATIN/IESCRIPTICN VALVE TIME *(SEC)

VAINE TDE* fSBC) t 92-A C24fr Vacuum Punp 1B & H2 Epnrunh. Suction (A)1V-1CV-150C 7.5 w

8 (A)1V-1CV-150D 7.5

j 1HY-102 N/A 1HY-104

.N/A

[

93-B CMfr Vacuum Punp 1A & H2 Recmb. Suction (A)TV-1CV-150A 7.5 4

(A)TV-1CV-150B

.7. 5 e

IHY-101 N/A E

'1HY-103 N/A n

94-C CNfr Vacuum Ejector Suction (11)HCV-1CV-151 N/A' (11)HCV-1CV-151-1 N/A

~

95-C RVLIS

- (2) (12)

N/A (2) (12)

N/A mu 5S 3e 95-64 H Analyzer - C24fr Dme

- (1)SOV-1HY-102B1 N/A (1)SOV-1HY-102B2 N/A 2

us e E h 95-69 H Analyzer - PRZR Cubicle (1)SOV-1HY-103B1 N/A (1)SOV-1HY-103B2 N/A 2

l 95-72 H Analyzer - Discharge (1)SOV-1HY-104B1 N/A

'(1)SOV-1HY-104B2 N/A 2

96-B High Head SI to Cold Iegs (3) (2)1SI-95 N/A (3) (2)fDV-3SI-836 N/A 97-1-A RHR Inlet Sanple (A)'1V-ISS-104A1 20 (A)TV-ISS-104A2 20 97-2-A RHR Outlet Sanple-(A)1V-1SS-103Al' 20 (A)TV-1SS-103A2 20 97-3-A 04fr Isakage Monitority Open Taps (A)'1V-11M-100h1 5.

(A)'1V-IIM-100h2.

5 97-4-A Steam Generator 1C Blowdown Sanple Closed Systema N/A' (3) (2) (A)1V-ISS-117C 20 l 98-1-C Spare l

l'

'IABr.E 3 6-1 ONIADGEENT PDEIRATIGES MAXDUt MhKDEM PNP INSIIE SDCIE OUISIIE SHGE NO.-AREA IIBrfIFICATION/ffs.2umCN VAINE TIME *fSEC)

VALVE TDE* fSBC) 98-2-C Spetm E

g 98-3-C Spare l

i n

g:

98-4-C Spare i

C 4

99-C Spare Co 100-B Spare n

101-B Spare 102-B Spare

e s 103-A Refuelirs Cavity Purification Inlet IPC-38 N/A 110-37 N/A l

E h 104-A Refueling Cavity Purification Outlet IPC-9 N/A 110-10 N/A 105-1-B Steam Generator IB Blowdown Sa ple Closed Systen N/A

' (3) (2) (A)W-3SS-117B 20 l.

105-2-B PRZR Vapor Sample-(A)W-ISS-112A1 20 (A)W-ISS-112A2 20 105-3-B Spare 105-4-B Spare 106-SgD SI h m=0ator Test Line

- (A)MN-1SI-842 15 (A)W-ISI-889 7.5 107-C Spare i

108-B Spare 1

+ -

.-.p, e

.,go a

~~-.

,c,-

.-s yc g-

- ~ ~-

--ye--~e,-.N--

e-

.-p

,,w.,.en

.,+v.

g

TABEE 3o6-1 mermneerr PDEMATIWS MAxDur MaxIn m l

rDrr nem snam ansa su m No.-AREA IDBFTIFIGTIN/DESGIPTIN VALVE TIME *fSK3 VALVE TIME

  • fSBC) 109-C RVLIS (2) (12)

N/A (2) (12)

N/A' E

j 109-44 Inlet Mcw Suple - Offf Dcne (1)SOV-1HY-102A1 N/A (1)S07-1HY-102A2 N/A n

g 109-49 Inlet Flow Sample - PRZR Cubicle (1)SOV-1HY-103Al N/A (1)SOV-1HY-103A2 N/A 5

109-52 How Sanple Discharge (1)SOV-1HY-104A1 N/A (1)SOV-1HY-104A2 N/A k

110-1-C IRZR Dead Weight Calibrator PP-10-45SA' Closed System N/A (1)1RC-277 N/A (1)1RC-278 N/A 110-2-C Spare mv g3 no-3-C Spare l -

3e ga no-4-C Spare I

e3 in-C Spare (7) Flange N/A n2-C Spare (7) Flange N/A n3-1-A BIT to Cold legs

- (3) (2)1SI-94 N/A (3) (2)POV-ISI-867C 13(4)

(3) (2)POV-ISI-867D 13(4)

Primary Containment Airlock IM-P-1 l

Equalization Valve (1)1VS-169 N/A Equalization Valve (1)1VS-170 N/A Equalization Valve (1)1VS-167 N/A Equalization Valve (1)1VS-168

_N/A.

I TMEE 3.6-1 i

p PENEIRATINS' MAXDUt MRXDUt PENT INSIIE SIROEE CUISIIE FIIGE NO.-AREA INNTIFIGTION/IESGIFTICN VALVE TIME *fSEC)

VALVE TDE* fSEC)

Emtuma v Contairunent Airlock PH-P-2 w

E s

Equalization Valve (1) (7)1VS-184 N/A Eqmli7atica Valve (1) (7)1VS-183 N/A C

4 (A) Containment Isolation Ihase A (B) Containment Isolation Ihase B e

O n

(1)

May be opened on an intermittent basis under administrative control.

]

~

i (2)

Not subject to Type C leakage tests.

j mu gy o

3m (3)

Valves tested per specification 4.0.5.

I-m i en w

.i C#

(4)

Maximn opening t-iw.

j (5)

Applicability: During CORE ALTERATIONS or movement of irradiated fuel within cantairument.

l (6)

Not subject to the r%=:n=ad.s of specification 3/4.6.3.

Listed in TMEE 3.6-1 for infonmation only.

i (7)

Tested under Type (B) testing.

(8)

Not used.

1 (9)

Auto open on Safety Injectimi recirculatice signal.

(10)

Not subject to the surveillance requitunents of specification 3/4.6.3. Valves tested per specification 4.0.5.

(11)

Valve will be locked shut in modes 1, 2,~3 and 4.

'(12)

Isolation is provided by bellows up=u.at.(:d hydraulic isolators.

4 4

t CQtfTAllGRENT SYSTDt3 j

SURVEILLANCE R1oVIREIGitTS, (Con't) 4.

Verifying the integrity of all heater electrical l

circuits by performing a continuity and resistance to ground test inenediately following the above required functional test.

The resistance to ground for any heater phase shall be 1 10,000 ohms.

i

?

4 BEAVER VALLEY - UNIT 1 3/4 6-22 l

neoposer>

{

. CONTAINMENT SYSTEMS BASES

[

l P

3/4.6.2.3 CHEMICAL ADDITION SYSTEM The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.

The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized.

These assumptions are consistent with the iodine removal efficiency assumed i

in the accident analyses.

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analysis for a LOCA.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.

Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water 3) corrosion of metals within containment.

These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA."

l 1

BEAVER VALLEY - UNIT 1 B 3/4 6-3 PROPOSED WORDING 1

l ATTACHMENT A-2 Revise the Beaver Valley Unit No.

2 Technical Specifications as j

follows:

P Remove Pages Insert Paaes 3/4 3-32 3/4 3-32 3/4 6-22 3/4 6-22 4

3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24 3/4 6-25 3/4 6-25 3/4 6-26 3/4 6-26 3/4 6-27 3/4 6-27 3/4 6-29 3/4 6-29 3/4 6-30 3/4 6-30 3/4 6-34 B3/4 6-3 B3/4 6-3

?

I I

i l

l P

~

.~

~

TABLE 3.3 5 (Continued)

TABLE NOTATION I

Diesel generate starting and sequence leading delays included.

Response

time limit includes opening of valves to establish 51 path and attainment I

of discharge pressure for centrifugal charging pumps and low Head Safety injection pumps.

Sequential transfer of charging pump suction from the volume control tank (VCT) to the refueling water storage tank (RWST)

(RWST valves open, then VCT valves close) is not incloded.

i Diesel generator starting and sequence loading delays not included.

l Offsite power available.

Response time limit includes cpening of valves to establish $1 path and attainment of discharge pressure for centrifugal charging pumps.

Sequential transfer of charging pump suction from the l

volume control tank (VCT) to the refueling water storage tank (RWST) (RWST valves open, then VCT valves close) is included.

M Diesel generator starting and sequence loading delays in W ded.

Response

time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

Sequential transfer of charging pump suction from the volume control tank (VCT) to the -

refueling water storage tank (RWST) (RWST valves open, then VCT valves i

close) is included.

(1) Feedwater system overall response time shall include verification of valve s}roktmes app]icable to jy t:i;;;; =h;; ;h:r Sr ::::tnth:: ?i, (2) Diesel generator starting and sequence loacing delays included.

Response

time limit includes attainment of discharge pressure for service water pumps. (3) Diesel generator starting and sequence loariing delays g included. Response time limit only includes opening of valves to establish the flowpath to the diesel coolers. (4) D.iesel generator starting and sequence loading delays not included. Offsite power available. Response time limit. includes operati'on of valves / dampers. (5) Diesel generator starting, and sequence loading delays included.

Response

time limit includes operation of valves / damp *ers. (6) Diesel generator starting and sequence loading delays g included. Response time limit includes operation of dampers, h heheN Cda.Se>& jso/aftd ve/ye.g & MN ff. and A na fses%)u ylaA9 va/ves a byss.s valves k r~.', 4. BEAVER VALLEY - UNIT 2 3/4 3-32 $0845ED &9/?b/$ ..m. r - -,,,.... - +, s ,,.w. ,--s -e w.- ,..--.-,._,e-

TABLE 3.6-1 (Cont) 4 g

j CONTAIMENT PENETRATIONS m

i <K PENT. M4NIfRM PWullfRM i INSIDE STNDRE OUTSIDE STROKE NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIIE (SEC) g 60 tow Head Safety Injection (3)(2) 25I5-132 N/A (3)(2) 2 SIS-fWY88888 N/A j g Discharge (13) ~ i 61 Low Head Safety Injection (3)(2) 2515-130 N/A (3)(2) 2 SIS-99W8889 N/A Discharge (13) t 62 tow Head Safety injection (3)(2) 25I5-133 N/A (3)(2) 2 SIS-MOV88884 N/A I 1 Discharge (13) i g, 63 Quench Pump Discharge 2QSS-4 N/A (8) 2QSS-fWW101A < 60 (4) r EP*; g 2QSS-RV101A N/A (,, g 64 Quench Pump Discharge 2QSS-3 N/A (8) 2QSS-fDV1018 < 60 (4) gm 2QSS-RV1018 N/A 65 Fuel Transfer Tube (7) Flange N/A (2)(6) RISC-/O.1 N/A l 't 66 Recirc Spray Pump Section (8)(2) 2RSS-fDW1554 < 60 (4) i 67 Recirc Spray Pump Section (8)(2) 2R$5-pWV155C < 60 (4) { 68 Necirc Spray Pump Section (8)(2) 2RSS-fDV1550 : 60 (4) 69 Recirc Spray Pump Section (8)(2) 2RSS-NDV1558 < 60 (4) ( l 70 Recirculation Pump (2)(13) 2RSS-29 N/A (8)(2) 2RSS-fWV156A < 60 (4) Discharge (6) 2RSS-RV156A N/A -i i 71 Recirculation Pump (2)(13) 2RSS-31 N/A (10)(8)(2) 2RSS-feW156C < 60 (4) .f Discharge (6) 2R$5-RV156C N/A i .2.

TABLE 3.6-1 (Cont) CONTAINNENT PENETRATIONS E g mx! nun mxlMuN 1. p PENT. INSIDE STROKE OUTSIDE STROME Q NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) 73 Main Steam System "A" Closed System N/A (2) 2 MSS-101A S l Closed System M/A (2) 2 MSS-A0V102A N/A Closef System N/A (2) 2 MSS-50V105A N/A Closed System M/A (2)(6) 2 MSS-SV101A N/A Closed System M/A (A)(6) 2 MSS-SV102A N/A g Closed System N/A (,z)(6) 2 MSS-SV103A N/A %1 Closed System N/A [J)(6) 2"-SV104A N/A ' Closed System N/A ('J)(6) 2 MSS-SV105A N/A Steam Drains System Closed System N/A (2) 2$05-A0V111A-1 < 60 Closed System N/A (2) 2505-A0V1298 < 60 Steam Vent System Closed System N/A (;t)(6) 2SVS-PCV101A N/A Closed System M/A (d)(6) 25VS-HCV104' N/A 1 O P a ,e r5wv v n ',.- -*-"v- ,,ne>e---v. t-w- .--s, -w-er*e+ -r--i.e w ,e-.-ems =,. * =.

~ TABLE 3.6-1 (Cont) ~. g 4 CONTAIMMENT PENETRATIONS = i s MXIMUN MXIfWN ? PENT. INSIDE STROKE OUTSIDE STROKE Q NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) !?l 74 Main Steam System "B" Closed System M/A (2) 2 MSS-HYW1018 5 l c-5 ] Closed System M/A (2) 2 MSS-A0V1028 M/A Closed System M/A (2) 2 MSS-50V1058 N/A Closed System M/A (2)(6) 2 MSS-SV1018 N/A Closed System M/A (J)(6) 2 MSS-SV1028 N/A { g Closed System M/A (;t)(6)2 MSS-SV1038 N/A 3 D Closed System N/A . [2)(6) 2 MSS-SV1048 N/A gh Closed System M/A [2)(6)2 MSS-SV1058 M/A Steam Drains System Closed System N/A (2) 2SDS-A0V1118-1 < 60 Closed System M/A (2) 2SDS-A0V1298 < 60 I Steam Vent System Closed System M/A (2)(6) 2SVS-PCV1018 N/A Closed System N/A [2](6)2SVS-HCV104' N/A 4 f 4 I m...

1 TABLE 3.6-1 (Cont) A E CONTAINNENT PENETRATIONS 9 s MAXIMUN MXIMUN P PENT. INSIDE STROME OUTSIDE STROME O NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) n:;' e c 75 Main Steam Systen "C" Closed System N/A (2) 2M55-NYV101C 5 l Closed System M/A (2) 2 MSS-A0V102C N/A Closed System M/A (2) 2 MSS-50V105C M/A Closed System M/A (J)(6) 2 MSS-SV101C M/A Closed System M/A (2)(6) 2 MSS-SV102C N/A Closed System N/A [2)(6)2 MSS-SV103C N/A D. Closed System M/A (J)(3) 2 MSS-SV104C N/A 4chb Closed System M/A [1)(6) 2 MSS-SV105C N/A Steam Drains System Closed System N/A (2) 2S05-A0V111C-1 < 60 Closed System N/A (2) 2505-A0V1298 < 60 Steam Vent System Closed System M/A @)(6) 2SVS-PCV101C N/A Closed System N/A (1)(6) 2SVS-NCV104' N/A 76 Feedwater "A" Closed System N/A (2) 2FWS-NYV157A 7 (2) = -2" "/A l 77 Feedseter "8" Closed System M/A N_YV1578 7; 78 Feedwater "C" Closed System N/A (2) 2FWS-NYV157C -G-7 -(2) = 30 %/A l m-__---~ = - - - -, - -w-=--= >~- - ~ ~ ~ ~ ~

i TABLE 3.6-1 (Cont) E CONTAlleqENT PENETRATIONS S sli MAXIMUM MAXIMUM 4 P PENT. INSIDE STROKE OUTSIDE STROKE i O NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) 1 c-79 Aux Feed "A" (2) 2 M a" M/* (2) 2FWE-HCV100E N/A l 5 - (2) 2FWE-HCV100F N/A i -f2) 2 M -02A. l (2) M-tM M/A 80 Aux Feed "B" (2) ? M -!^^ M/A (2) 2FWE-MCV100C N/A I (2) 2FWE-HCV1000 N/A (2) M -03A M/A (2) 2 M -t3" 9/^. g 83 Aux Feed "C" (2) " '-1^1 M/" (2) 2FWE-HCV1004 M/A l ~ o R (2) 2FWE-HCV1006 N/A D* (2) 2 M tif.- M/A l M ? - (2) 2 M -100 M/A i @ 3: 87 Hydrogen Recombincr N/A (1) 2HCS-MDV117 N/A i ilischarge (1) 2MCS-111 N/A i 88 ",1 4 3 Recce6iner N/A (1) 2HCS-MDV116 N/A l, Discharge (1) 2HCS-110 N/A l 89 SPARE 90 Purge Doct Exhaust (5) 2HVR-MDB238 10 (M)(5) 2NVR-MOD 234 10 f l ~ (5) 2HVR-MD0258 10 [N)(5)2HVR-MDB254 10 91-Purge Duct S w ly (N) (5) 2HVR-DNP206 - N/A 92 Hydrogen Recon 6iner (1) 2HCS-50V1148 N/A

  • Isolation (1) 2HCS-50V1158 N/A Reactor Cont. Vacuum

.(A) 2CVS-50V1518 < 60 Pump Suction (A) 2CVS-50V1528 < 60 5 y w,-- 9 w -+ y-r- .u- --r. ,,,v-,,v- -, - + -,, c ,,r w - -w..y y e-w.,~,&.. .--,+.,-e-,.. ,e

TABLE 3.6-1 (Cont) CONTAINNENT PENETRATIONS 5E MXIMUN MAXIMUM E PENT. INSIDE STROKE OUTSIDE STROKE O NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) c 93 Hydrogen Recombiner (1) 2HCS-50V114A N/A } Isolation (1) 2HCS-50V115A N/A Reactor Cont. Vacuus (A) 2CVS-50V151A < 60 Isolation (A) 2CVS-50V152A < 60 94 Ejector Section [/4) 2CVS-151 N/A (W) 2CVS-151-1 N/A l SPARE 97 Leakage Detection (2) 2LMS-50V952 < 60 (4) g,* Blowdown Sample Closed System N/A (2) 2SSR-A0V117C < 60 hb Liquid Sample - Cont. (1)(A) 2SSR-50V129A-1 < 60 (1)(A) 2SSR-50V1294-2 < 60-Sump & RMS 2SSR-RV122 N/A !!,J. w.-. Analyzer (1) 2HCS-50V1338 N/A (1) 2HCS-50W1348 N/A 98 SPARE 99 Hose Rack Supply 2FPW-761 N/A (A) 2FPW-A0V206 < 60 100 SPARE 101 Reettor Cont. Deluge - 2FPW-753 N/A (A) 2FPW-ADV205 < 60 Cab"le Pent. Area & RMS Pump 103 Reactor Cavity Purif Inlet 2FNC-121 N/A 2FNC-38 N/A 104 Reactor Cavity Purif 2FNC-122 N/A 2FNC-9 N/A Dutlet

TABLE 3.6-1 (Cont) h CONTAllMENT PENETRATIONS y mxinun mx1Mun E PENT. INSIDE STROKE OUTSIDE STROKE O NO.-AREA IDENTIFICATION / DESCRIPTION VALVE TIME (SEC) VALVE TIME (SEC) g 118 Quench Spray System 2QSS-267 N/A (11)(B)(1) 2QSS-50V1004 N/A (11)(B)(1) 2QSS-50V1006 N/A " 119 RVLIS 12) N/A 12,) N/A Primary Containment Personnel Air Lock 2 PHS-PAL 1 i Equalizing Valve-(f)(7) 2PHS-112 N/A Equalizing Valve (t)(7) 2PHS-113 N/A Equalizing Valve (1) (7) 2PHS-101 N/A j k og Equalizing Valve (1) (7) 2PHS-110 N/A b= Equalizing Valve ( i) (7) 2PMS-111 N/A 04p Equalizing Valve (l)(7) 2PHS-100 N/A h Emergency Containment Air Lock 2PHS-EAL 1 Equalizing Valve (1)(7) 2PHS-202 N/A Equalizing Valve (f) (7) 2PHS-201 N/A 4 1 9 6 e .a ' I .n. --y ... s o, ~n , ~ - -. ,;,,n n.

i TABLE 3.6-1 (Cont) EE (A) Containment Isolation Phase A. l <E (B) Containment Isolation Phase B. E 7 (1) May be opened on an intermittent basis under administrative control. (2) Not sdject to Type C leakage tests. (3) " - ' - ' - "

  • - * ' " * ' - ^ - - - ' ' * ~ * " "

w @vi3 Ns10 'lYs' 705 ' ' ' ' ~ Maximus opening time.,ide?h"c;.h f l (1) (5) Applicability: During CORE ALTERATIONS or novement of irradiated fuel within containment. -T h p.eht.:.; ;f W atficati= 3.2.* :

; z?ht h.

T h = ;.".;i. 2..^. T., g E L -.t _: : :,,17 :ha., - ri!! k Sch' f _^. _'_- h;;; g;. ;".i= h : f;; 1, 2, 3, =' 4. 37d w1 (6) Not subject to the requirweents of Specification 3/4.6.3. Listed in Table 3.6-1 for information only. o. g J. (7) Tested under Type "B" testing. T,ef use/ N (8) -1y. _.;d-and g.. ^ eti-pt;;- f. I (9) Auto open on Safety Injection recirculation signal. (10) Auto close on Safety Injection recircelation signal. (11) Auto open on QSS switchover signal. (12) Isolation is provided by bellows operated hydraulic isolators. (13) Not subject to the serveillance requirements of specification 3/4.6.3. Valves tested per specification 4.0.5. hlf) Vsive will be lockel shuf ir !! ale,s 1,2,3 a.,/ y. c l 6 - ~~^

l MAllMENT SYSTEMS 3/4\\.5$USATMD$PHERICPRESSURECONTROLSYSTEM $ TEAM \\TAIREJECTOR ) \\ITION FOR OPERAT10N 11MITINC C0 3 6.5.1 The ins e and outside manual isolation valves in the steam t air ejectorsuctionli shall be closed. APPLICABILITY: MODES, 2, 3, and 4. ACTION: With the inside or outside nual isolation valve in the at ajetairejector suction line not closed, rest e the valve to the closed sition within 1 hour or be in at least HOT STAND 8Y thin the next 6 hours an COLD SHUTDOWN within, l the following 30 hours. SURVEILLANCE RfoulREMENTS 4.6.5.1 1 The staan jet air ejector suct 1 outside manual isolation valve shall be determined to be in the closed pos on by a visual inspection prior to increasing the Reactor Coolant System t sture above 350*F and at least ( once per 31 days thereaf ter. 4.6.5.1.2 Thesteamjetairejectors tion line side manual isolation valve shall be determined to be sealed o.r 1 Aed in the c sed position by a visual ins 350gettionpriortoincreasingthe actor Coolant S tem temperature above F. e AVER VALLEY - UNIT 2 3/4 6-34 h&$STE ,w-- - ~, - < - 4 ---w. ,-,-nw~- <-,-w-, ,_r-s---.w--,w-, --oo-,e-

( b CONTA!NMENT SYSTEMS i ( RAiF1 l f i 3/4.6.4 COM6USTIBLE GAS CONTROL l The OPERABillTY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post LOCA conditions. Either recombiner unit is capable of con-trolling the expected hydrogen generation associated with 1) zirconium water l reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentra-tions in Containment Following a LOCA." i W SUBATMOSPHERIC PRESSURE CONTROL SYSTEM f 3/4.6.5. EJECTOR I The closure of the manual iso valves in the suction of t jet air ejector ensures that 1) the conte

ter y be i

osintained within its operation limits cuum pumps and 2).the containment atmos h ed from the outside nt in the event of a va ves are required to be closed for conta' (} 4 P e i V 8EAVER VALLEY - UNIT 2 8 3/4 6-3 fk0h0360 k)0Mb/A/V

ATTACHMENT B i safety Analysis Beaver Valley Power Station Proposed Technical Specification Change Unit No. 1 Change No. 160 tinit No. 2 Chanae No. 20 Description of amendment request: The proposed amendment would correct the containment isolation valve listing in Table 3.6-1 and clarify the applicable notation. The following corrections have been incorporated: A. BV-1 TS Table 3.3-5 items 2.C, 3.C and 4.C have been revised to change the feedwater isolation time to s 13.0 seconds to be consistent with the most limiting time listed for feedwater isolation in item 6.b. UFSAR pages 7.3-3, 7.3-13 and 14.2-16 take licensing credit for the safety function of the feedwater regulating valves (FCV-rW-478, 488, 498) as the prinary means for feedwater isolation. This was implemented into the TS in i Amendment No. 120 only for feedwater isolation on steam generator water level--high-high.

However, since this is currently the most limiting criteria, this isolation time will be implemented throughout the rest of Table 3.3-5 for consistency and to avoid confusion. -When Amendment No. 120 incorporated the 13 second response
time, a

rote (2) was applied. Note (2) was then inadvertently replaced by i Amendment No. 138. Since all feedwater isolation times will now be the

same, note (1) has been revised to reference the I

feedwater regulating and bypass valves and is applied to items i l 2.C, 3.C, 4.C and 6.b. Similar to the BV-1 change, BV-2 Table 3.3-5 page 3/4 3-32 has been revised to reference the feedwater regulating and bypass valves in lieu of Table 3.6-1. B. The requirements of specification 3.6.5.1 concerning the steam jet air ejector isolation valves are satisfied by the note (valve will be locked shut in Moden 1, 2, 3 and 4) applied to both units listing for the steam jet air ejector penetration. Therefore, specification 3.6.5.1 and associated bases are l being deleted. C. DV-1 Technical Specification (TS) Table 3.6-1 has been modified by incorporating the following changes: 1. Note (1) (May be opened on an intermittent basis under administrative control.) has been applied to the following valves in addition to the valves currently specified in TS Table 3.6-1: -t + -.--r-r w--. . ~ -

Attcchment B r Page 2 Penetration Valve Raason ~ 95-64 SOV-HY-102B1, SOV-HY-102B2 Note (1) has been added to 95-69 SOV-HY-103B1, SOV-HY-103B2 these valves to be 95-72 SOV-HY-104B1, SOV-NY-104B2 consistent with the testing i 109-44 SOV-HY-102A1, SOV-HY-102A2 required to demonstrate 109-49 SOV-HY-103A1, SOV-HY-103A2 operability of the hydrogen r 109-52 SOV-HY-104A1, SOV-HY-104A2 analyr. ors in accordance with surveillance requirement 4.6.4.1. 3. Note (3) has been replaced with " Valves tested per specification 4.0.5" and is applied to the following valves to incorporate the results of the NRC evaluation contained in l Technical Specification Amendment No. 65: f Penetration Valves 7-A SI-83, MOV-SI-869A 15-A CH-31, MOV-CH-289 33-C SI-84, MOV-SI-869B 35-A MOV-CH-308A 36-A MOV-CH-308B 37-A MOV-CH-308C 39-C TV-BD-100A 40-A TV-BD-100B 41-B TV-BD-100C 46-A FCV-CH-160 56-4-A TV-SS-117A 60-SGD SI-13, MOV-SI-890A, SI-451 61-SGD SI-10, SI-11, SI-12, MOV-SI-890C 62-SGD SI-14, MOV-SI-890B, SI-452 68-SGD MOV-SI-860A i 69-SGD MOV-SI-860B 96-B SI-95, MOV-SI-836 97-4-A TV-SS-117C 105-1-B TV-SS-117B 113-1-A SI-94, MOV-SI-867C, MOV-SI-867D 4. Note (4) applies to the following valves to identify valve opening time instead of valve closure time (this note was not previously applied to MOV-SI-867C, D). This is consistent with UFSAR Table 5.3-1. Penetration Valves 63-SGD MOV-QS-101B 64-SGD MOV-QS-101A 66-SGD MOV-RS-155A 67-SGD MOV-RS-155B 70-SGD MOV-RS-156B 71-SGD MOV-RS-156A 113-1-A MOV-SI-867C, MOV-SI-867D

Attcchment B Page 3 I 5. Note (5) (Applicability: During core alterations or movement of irradiated fuel within containment) and note (11) (Valve will be locked shut in modes 1, 2, 3 and 4) have been added to the purge supply and exhaust isolation valves for penetrations 90 and 91. Note (5) provides the applicability requirements and note (11) provides the control requirements. These notes replace note (5) currently applied to those valves in TS Table.3.6-1. 6. Note (11) has been added to the steam jet air ejector suction isel4 tion valves for penetration 94. Note (11) j provides the control requirements (Valve will be locked shut 1 in Modes 1, 2, 3 and 4). This is consistent with note (13) ) applied to the containment isolation valves listed for penetrations 90 and 91 and satisfies the requirements of specification 3.6.5.1. 7. The term RVLIS has been added to penetrations 95C and 109-C and note (12) applied to indicate isolation is provided by bellows operated hydraulic isolators. 8. The main steam trip valve bypass valves MOV-MS-101A, B and C have been added to penetrations 73-SGD, 74-SGD and 75-SGD to reflect the main steam trip valve TV-MS-101A, B and C bypass valves identified in UFSAR Figure 10.3-1. Note (1) (May be l opened on an intermittent basis under administrative ( control) has been applied to these 2 inch bypass valves to allow pressure equalization across the trip valve disc and warming of the main steam lines when the trip valve is closed. The valve closure time for the main steamline drain valves TV-MS-111A, B, C has been changed from 10 seconds to 8 seconds consistent with Table 3.3-5 for steamline isolation. l The main steam residual heat release valve HCV-MS-104 has been added to penetrations 73-SGD, 74-SGD, 75-SGD in i accordance with the current UFSAR Table 5.3-1A. Note (1) (May be opened on an intermittent basis under administrative control) has been applied to this valve since this valve may be opened to release the sensible and core residual heat as described in UFSAR Section 10.3.1.2. Note (6) has also been added to this valve to document that this valve is listed for information only. 9. FH-1 has been added to penetration 65 to identify the manual l valve outside containment. This valve is not required to be Type C leak tested due to the double barrier seal arrangement on the fuel transfer tube inside containment isolation flange. Therefore, note (6) has been added to document that this valve is listed for information only. See the attached change to UFSAR Section 5.3. l 'l re,c*-rw mWN "f

Attcch :nt B f Page 4 l f i 10. The valve actuation time for penetration 113-1-A isolation valves MOV-SI-867C and MOV-SI-867D has been changed from 15 i to 13 seconds. This corrects an inconsistency with the SI minimum response time provided in TS Table 3.3-5. 11. The equalization valves listed in TS Table 3.6-1 for the l personnel and emergency airlocks identified with note (8) (Temporarily removed and penetration plugged) will remain i

plugged, therefore, those valves have been removed from the table.

Note (8) no longer applies to any penetration listed on this table and has been deleted and identified as (Not used). The equalization valves added to the table for the emergency airlock are mechanically operated by the door -r opening and closing mechanism. Notes (1) (May be opened on t an intermittent basis under administrative control) and (7) l (Tested under Type D testing) have been applied to the emergency airlock equalization valves since for note (1) these valves must be opened to use the airlock and for note i (7) these valves are tested when the airlock is pressurized i for Type B testing as described in UFSAR Section 5.2.4.8. Note (1) has also been applied to the personnel airlock since the equalization valves must be opened to use the airlock. The equalization valves for the personnel airlock are Type C tested and are also subjected to the airlock pressure during Type B testing. 12. The main feedwater isolation valves listed in TS Table 3.6-1 for penetrations 76-SGD, 77-SGD and 78-SGD have been changed to reflect the appropriate penetration class and valve configuration. These are class B penetrations as stated in UFSAR Table 5.3-1 and in accordance with UFSAR Section l 5.3.2, satisfy the arrangement described in UFSAR Section 5.3.1.2(e) which specifies a sealed system inside containment and one isolation valve outside containment that is either automatic or normally shut and administrative 1y controlled, or capable of remote manual operation. These penetrations are shown in UFSAR Figure 10.3-5 and show that FCV-FW-478, 488 and 498 are upstream of MOV-FW-156A, B and C. All of these valves are currently listed in TS Table 3.6-1,

however, MOV-FW-156A, B

and C are closest to l containment and are installed Class Q2 in accordance with UFSAR Section 6.2.2.1 which requires Class Q2 piping on l those portions of systems used for containment isolation. l FCV-FW-478, 488 and 498 are not installed in Class Q2 piping and therefore do not satisfy the criteria for a containment isolation valve and have been removed from the table. t ~- ~ ..-e ~ +

. Attachment B Page 5 The auxiliary feedwater piping connects to the main feedwater piping down stream of the main feedwater isolation valve before the main feedwater piping enters containment as shown in UFSAR Figure 10.3-5. The auxiliary feedwater piping is Class Q2 from the main feedwater piping to and including the check valva shown in the figure and in accordance with our request for exception to GDC-57 (provided by letter dated July 8, 1989) these check valves (FW-42, 43 and 44) will be listed as the auxiliary feedwater containment isolation valves. In accordance with GDC-57, only the following valves are required to be listed for these penetrations: Penetration Valves 76-SGD MOV-FW-156A, TW-42 77-SGD MOV-FW-156B, FW-43 78-SGD MOV-FW-156C, FW-44 The valve closure time for the main feedwater containment isolation valves (penetration 76-SGD, MOV-FW-156Al 77-SGD, MOV-FW-156B; 78-SGD, MOV-FW-156C) has been changed from 75 seconds to N/A. UFSAR pages 7.3-3 and 14.2-16 state that feedwater isolation is accomplished by closing all main feedwater control valves, feedwater pump trip and closure of the main feedwater pump discharge valves (MOV-1FW-150 A, B). The UFSAR takes no licensing credit for the feedwater containment isolation valves (MOV-1FW-156A, B, C) receiving a feedwater isolation signal and thus needs no response time for that function. The UFSAR does take credit for the feedwater containment isolation valves for containment isolation. However, any flow stoppage out of containment is accomplished by the check valve nature of its design. The MOV only provides remote manual operation as required by General Design Criteria (GDC) 57 as a backup feature since a check valve can not be used by itself in this application. These valves need to maintain (and be tested for) their MOV operability but need no time response limitations due to safety analyses considerations. Thus these valves function similar to other MOVs in Technical Specification Table 3.6-1 with a "N/A" maximum stroke response (e.g., MOV-1CC-112A2 or MOV-1SI-869A.) i i i 1 u

AttCchment B j Page 6 13. Note (2) was added to the following valves since they are not Type C tested (See items 7, 8, 9, and 12 also)t EADetration Valves 65 FH-1 73 MOV-MS-101A, HCV-MS-104, PCV-MS-101A, Safety Valves 74 MOV-MS-1018, HCV-MS-104, PCV-MS-101B, Safety Valves 75 MOV-MS-101C, HCV-MS-104, PCV-MS-101C, Safety Valves 76 FW-42 77 FW-43 78 FW-44 95 RVLIS 109 RVLIS FH-1 is not required to be Type C leak tested due to the double barrier seal arrangement on the fuel transfer tube inside containment isolation flange. The main steam and RVLIS are also not required to be Type C leak tested because they are located on sealed systems that do not communicate with the RCS or containment atmosphere. a i 14. The following changes have been incorporated to reflect UFSAR Table 5.3-1: Penetration Chance 13-D add note (A) to TV-FP-107 31-D add note (A) to TV-FP-105 32-C add note (A) to TV-FP-106 95-C & 109-C add RVLIS and identify with note (12) similar to BV-2 (Isolation is provided by bellows operated hydraulic isolators) D. BV-2 Table 3.6-1 has been modified by incorporating the following changes: 1. Note (5) (Applicability: During core alterations or movement of irradiated fuel within containment) and note (14) (Valve will be locked shut in Modes 1,2,3 and 4) have been added to the purge r.upply and exhaust isolation valven for penetrations 90 and 91. Note (5) provides the applicability requirements and note (14) provides the control requirements. These notes replace note (5) currently applied to these valves in TS Table 3.6-1. 2. Note (14) has been added to the steam jet air ejector suction isolation valves for penetration 94. Note (14) provides the control requirements (Valve will be locked shut in Modes 1, 2, 3 and 4). This in consistent with note (14) applied to the containment isolation valves listed for penetrations 90 and 91 and satisfies the requirements of specification 3.6.5.1. T v n v

Attochment B Page 7 3. Note (1) (May be opened on an intermittent basis under administrative control.) has been applied to the personnel and emergency airlock equalization valves since these valves must be opened to use the airlocks. 4. Note (8) (Temporarily removed and penetration plugged) is not applicable to any penetration listed on this table and has been deleted and identified as (Not used). 5. 21SC-102 has been added to penetration 65 to identify the manual valve outside containment. This valve is not required to be Type C leak tested due to the double bhrrier seal arrangement on the fuel transfer tube inside containment isolation flange. Therefore, note (6) has been added to document this valve is listed for information only. 6. Note (3) has been revised consistent with BV-1 note (3) to specify these valves are tested in accordance with specification 4.0.5; this is consistent with the current note and provides clarification. 7. Note (2) has been added to the following valves since they are not Type C tested: Penetration valves 65 2ISC-102 73 Safety Valves, 2SVS-PCV101A, 2SVS-HCV104 74 Safety Valves, 2SVS-PCV101B, 2SYS-HCV104 75 Safety Valves, 2SVS-PCV1010, 2SVS-HCV104 119 RVLIS The fuel transfer tubu gate valve 2ISC-102 is not required to be Type C leak tested due to the double barrier seal arrangement on the fuel transfer tube inside containment isolation flange. The safety, relief and RVLIS are also not required to be Type C leak tested because they are located on sealed systems that do not communicate with the RCS or containment atmosphere. 8. The following valve numbers have been changed to reflect UFSAR Table 6.2-60 Change Change Penetration from to 73 2 MSS-HYV101A 2 MSS-AOV101A 74 2 MSS-HYV101B 2 MSS-AOV101B 75 2 MSS-HYV101C 2 MSS-AOV101C l

'Attcchment B Page 8 9. For penetrations 76, 77, 78 the feedwater containment isolation valves closure time has been changed from 5 cec. to 7 sec. These valves receive a Train A feedwater isolation signal in accordance with TS Table 3.3-5 which specifies 7 sec. for feedwater isolation. Therefore, it is acceptable for valve stroke times of greater than 5 sec. as long as the total time including signal processing is less than 7 sec. 10. The main feedwater and auxiliary feedwater systems are closed systems which enter containment through penetrations 76, 77, 78, 79, 80, 83 and in accordance with GDC 57, the isolation arrangement for these penetrations is satisfied by one automatic valve outside containment. Therefore, the following valves currently listed for these penetrations are not required and have been deleted from the table Valve Egnetration Inside outside 76 2FWS-28 77 2FWS-29 78 2FWS-30 79 2FWE-99 2FWE-42A,B 80 2FWE-100 2FWE-43A,B 83 2FWE-101 2FWE-44A,B These changes will not affect the limiting conditions for operation or surveillance requirements. Changes to the valve listing have been made to correct errors and improve the notation applicable to the valves. Therefore, the proposed amendment will not result in an increase in the probability or consequences of a previously evaluated accident or reduce the safety of the plant, i l l l l

  • . i.

i ATTACEMENT C No Significant Hazard Evaluation Beaver Valley Power Station Proposed Technical Specification Change Unit No. 1 Change No. 160 2 1 Unit No. 2 Chance _N_o. 20 r l Basis for Proposed No significant Hazards Consideration i Determination: The Commission has provided standards for determining whether a significant hazards consideration exists in accordance with 10 CFR 50.92(c). A proposed amendment to an I operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the i l proposed amendment would not (1) involve a significant increase in l the prcbability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind L of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. i' The proposed changes do not involve a significant hazard consideration because: 1. Changes to the valve listing have been made to correct errors and improve the notation applicable to the valves. Therefore, these changes are administrative in nature and will not involve a significant increase in the probability of occurrence or consequences of an accident previously analyzed. 2. The requirements of specificatien 3.6.3.1 will continue to govern the operability of the containment isolation valves. The proposed change does not introduce any new mode of plant operation or require any physical modification to the plant. Therefore, these changes will not create the possibility of a new or different kind of accident from any accident previously evaluated in the FSAR. 3. The proposed changes will not reduce the operability of the containment isolation valves or change the functional test requirements. The proposed changes will not affect any of the plant setpoints or margins to the accident analysis limits or technical specification limits and therefore, will not involve a significant reduction in the margin of safety of the plant. Therefore, based on the above considerations, implementation of the proposed changes will not involve a significant hazard.

e' ATTACIDENT D. Beaver Valley Power Station, Unit No. 1 f a UFSAR Changes Proposed Technical Specification Change No. 160 t i I V +

o' e o; e Chances to UFSAR Table 5.3-1 Rearrange the listing by penetration number, and Penetration Chances 24 Add RH-16 to reflect UFSAR Figure 9.3-1. 44 Delete this check valve since it would not isolate a pressurized containment atmosphere during accident conditions. 73, 74, 75 Add the main steam trip valve bypass valves MOV-MS-101A, B and C and the RHR valve HCV-MS-104 to reflect UFSAR Figure 10.3-1. 76, 77, 78 Delete the manual valve listed, Replace the remote-manual valve with a check valve, and Replace the isolation valve position for normal and shutdown with closed, Replace the 1971 GDC or Exception Het to FSAR 5.3.3.9, Replace the outside valve closure time with check, Replace the outside valve type with check, Replace the outside power source with check. 92, 93 Revise the valve listing for these penetrations to reflect DCP-621 and Technical Specification Amendment No. 127 (removed the hydrogen recombiner inside containment check valve internals), and Replace the inside valve with none, Replace the 1971 GDC or Exception Met with FSAR 5.3.3.8, For both the 2 auto trip in series and the 2 manual valves: Change the inside valve closure time to none, Change the inside type to none, Change the inside power source to none. 90, 91 Delete the discussion under auto actuation signal, this information is addressed in note 7. Add note 11 (Valve is locked shut in Modes 1, 2, 3 & 4) to these valves to reflect Figure 5.4-1. 94 Add note 11 to these valves to reflect the deletion of specification 3.6.5.1.

o' o ** *: ) ' Chances to UFSAR Table 5.3-1 l Page 2 Personnel Airlock I Correct the mark number from PM-P-1 to PH-P-1. Correct the isolation valves listed, these are Class D penetrations and the valves are normally closed and. administratively controlled: One manual valve is listed for both the inside and i outside of each containment airlock door, two of the valves are used to equalize pressure when, entering containment and the other two valves are used to equalize pressure when exiting containment. Change the isolation _ valve failure position from closed to AS-IS, to reflect the manual valves. Change the power source for both inside and outside isolation valves from none to manual. Emergency Airlock correct the mark number from PM-P-2 to PH-P-2. Change the isolation valve failure position from closed [ to AS-IS, to reflect the manual valves. Change the power source for both inside and outside l isolation valves from none to manual. i Notes (11) Add this note " Valve is locked shut in Modes 1, 2, 3 and 4" to reflect Figure 5.4-1. t t-l ? r

~~_ ... e BVPS-1-UPDATED FSAR Rov. 5 (1/07) l relative void content. Connections at the reactor vessel

head, hot legs A

and B, and the seal table provide the RVLIS sensing points. Tubing from these connections runs to high volume sensors which isolate j-RVLIS tubing. The remainder of RVLIS tubing is filled the reactor coolant. system from the remainder of the with deaerated domineralized water. capillary tubing runs from the high.. volume sensors, penetrates the containment =. and runs to the hydraulic + isolators. Tubing then connects the h/draulic isolators to differential pressure transmitters. Containment isolation is provided by the high volume

sensor, hydraulic
isolator, and connecting. capillary tubing.

Within the high volume sensor is a check valve which will close under reactor coolant system pressure if the + connecting capillary tubing fails. Containment Hydrogen Monitoring System lines and RVLIS lines pass through containment penetrations 95 and-109. RVLIS lines that penetrate the containment structure conform to the intent of General Design Criterion 57. Suejbo% and 8. Post DBA Hydrocen Control ^ Discharae to Containment (Penetrations 87-end-88K f;L eta d fJ f/)SS W b -u... ,s... u.... n .u u.,, ...,...2.

t
id;
t; inn;;t chi;h nera;ily
1;;;;

and idritirtr:ti :17

tr:11:d.

The valves are located as close as possible to the containment wall.. The piping meets the break / crack exclusion criteria set forth in Branch Technical Position MEB 3-1, Postulated Rupture Locations, an Flyid System Piping Inside and Outside h Containment as ass. The post DBA Hydrogen Control-System is part of the Engineered Safety Features and the system's normally closed containment isolation valves IA/SE4r A must be opened manually by the operator for long-term hydrogen control. Shortly after a DBA, the ambient temperature within the containment l may be as high as 280'F. Although such high temperatures are short lived (the containment is reduced to subatmospheric conditions in less than 60 minutes as the containment depressurization system, i Section 6.4, cools the containment atmosphere), it is possible that water trapped in the lines of the systems isolated by the containment isolation system may expand more rapidly than the associated piping. This could result in pressures exceeding the design pressure of_the piping. To ensure that such overpressurization of isolated piping cannot adversely affect containment isolation integrity, a relief valve set to relieve at a pressure below the design pressure of the 5.3-12 ---w a.it- - - - - -w w--+w--o.- wre-W ,-,e .-y ,,+g-e-- ap-9.yy-c. -g

  • .gy.-p

-.-a

~ o da o* n'$ o INSERT A i 9. Auxiliary Feedwater Pumn Discharae (Penetration 76. 77, and 78) ) The auxiliary feedwater piping connects to the main feedwater piping downstream of the main feedwater isolation valve before the main feedwater piping enters containment as shown in Figure 10.3-5. The auxiliary feedwater piping is Class Q2 from the main feedwater piping to and including the check valve shown in the figure. An exemption from the requirements of GDC-57 was required for the auxiliary feedwater conteinment. isolation configuration since a simple check valve pruvides i the isolation function outside containment. This configuration was found acceptable by the NRC since this i design was licensed at Virginia Electric Company's North Anna plants. INSERT B The hydrogen recombiner suction lines have 2 inch manual ball j valves in series outside containment which are normally closed and administratively controlled. These lines connect to the i containment vacuum pump suction-lines between the two in series auto trip isolation valves and containment penetrations 1 92 and 93. The hydrogen recombiner discharge lines have two 2 inch manual ball valves in series outside penetrations 87 and 1 88 which are normally closed and administratively controlled. J i i i i 1 1 \\ I m ~ -}}

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