Text

Amend 63 to License DPR-65,adding Operability,Trip Setpoint & Surveillance Requirements for Automatic Initiation of Auxiliary Feedwater Sys
	ML20003A169
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Site:	Millstone
Issue date:	01/14/1981
From:	Clark R; Office of Nuclear Reactor Regulation
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4, UNITED STATES NUCLEAR REGULATORY COMMISSION o

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-l WASHINGTON, D. C. 20585

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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY

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THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET HO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT E. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. OPR-65 t

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

1.

A.

The applications for amendment by Northeast Nuclear Energy Company (the licensee) dated March 31, May 20 and August 29, 1980, comply l

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 conformity with the application, the provisions of the Act, and the rules and regulations of I

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; I

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 requirements have been satisfied.

l 8101290 % %

2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, cnd paragraph 2.C.(2) of Facility Operating License No. OPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on January 20, 1981.

FOR THE NUCLEAR REGULATORY COMMISSION R. A. Clark, Chief

~

Operating Reactors Branch f3 Division of Licensing

Attachment:

Changes to the Technical Speci fications Date of Issuance: January 14, 1981 1

O s

,w 4

l l

ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the \\ppendix A Technical Specifications with the enclosed pages. The revised pages i

vertical lines indicated the area o,'re identified by Amendment number and conta change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages XVII 3/4 3-13 3/4 3-14 3/4 3-15 I

3/4 3-16 3/4 3-17 3/4 3-20 3/4 3-21 3/4 3-22 3/4 3-24 3/4 7-4 3/4 7-5 B 3/4 7-2

l' INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...............

6-17 6.9.2 S P E C I A L R E P 0 R TS..........................................

6-21 6.10 REC 3RD RETENTION..........................................

5-22 t

6.11 RADI ATION PROTECTION PR0 GRAM........................ '.....

6-23 6.12 HIGH RADIATION AREA.......................................

6-23 6.13 ENVIRONMENTAL QUALIFICATION...............................

6-24 l

1 l

MILLSTONE - UNIT 2 XVII Amendment No. 77, 36. 63

TABLE 3.3-3 (Continued)_

l ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENIATION 8

x P

MINIMIM C

TOTAL NO.

CilANNELS CilANNELS APPLICABLE y

FllNCT10NAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

'n 4.

MAIN STEAM LINE e

g ISOLATION

[

Steam Generator 4

2 3

1,2,3(c) 2 l

i Pressure - Low 5.

ENCLOSURE BUILDING FIL1 RAT 10N (EBFAS) a.

Manual EBFAS (Trip Buttons) 2 1

2 1,2,3,4 1

l b.

Manual SIAS (Trip Buttons) 2 1

2 1,2,3,4 1

l

,s" c.

Containment Pressure -

liigh 4

2 3

1, 2, 3 2

l w

<l. Pressurizer Pressure -

Low 4

2 3

1,2,3(a) 2 l

6.

CONTAINMENT SlMP RECIRCULATION (SRAS) i a.

Manual SRAS (Trip t

[

Buttons) 2 1

2 1,2,3,4 1

l

~

n

,E b.

Refueling Water Storage s,

Tant - Low 4

2 3

1, 2, 3 2

E N

O

TABLE 3.3-3 (Continued) 3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION p

MINIMUM 16 TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CllANNELS TO TRIP OPERABLE MODES ACTION Ey 7.

CONTAINMENT PURGE VALVE ISOLATION I

y a.

Manual CIAS (Trip Buttons) 2 1

2 1,2,3,4 1

l b.

Manual SIAS (Trip i

Buttons) 2 1

2 1,2,3,4 1

1 1

R c.

Automatic CIAS i

Actuation Logic 2.

I 2

1,2,3 1

l Y

Z d.

Containment Radiation -

Higli Gaseous Monitor 1(d) 1(dl 1

1,2,3,4,6 3

Particulate Monitor 1(d) 1(dh 1

1,2,3,4,6 3

a 8.

LOSS OF POWER a.

4.16 kv Emergency Bus h"

,Undervoltage (Under-voltage relays) - level one 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 2

l l

b.

4.16 kv Emergency Bus Undervoltage (Under-voltage relays) - levt:1 l

l 0

two 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 2

i I

e mm

--m m e+e e

m

TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed when pressurizer pressure is <

1750 psia; bypass shall be automatically removed when pressurizer pressure !! > 1750 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Trip function may be bypassed below 600 psia; bypass shall be automatically removed at or above 600 psia.

(d) Each channel has two sensors, high radiation level on either sensor will initiate containment purge valve isolation.

(e) Trip may be bypassed d" ring testing pursuant to Special Test Excep-tion 3.10.3.

i ACTION STATEMENTS E

ACTION l With the number of OPERABLE channels one less than the l

Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

With the number of OPERABLE channels one less than the l

ACTION 2 To'tal Number of Channels and with the pressurizer pressure:

1750 psia; imediately place the inoperable s.

4 channel in the bypassed condition; restore the in-operable channel to OPERABLE status prior to increa-sing the pressurizer pressure above 1750 psia.

b.

> 1750 psia, operation may continue with the in -

_operable channel in the bypassed condition, provided the following conditions are satisfied:

1.

All functional units receiving an input from the bypassed channel are also placed in the bypassed condition.

i 2.

The Minimum Channels OPERABLE requirement is i

met; however, one additional" channel may be l

removed from service for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 l

provided one of the inoperable channels is j

placed in the tripped condition.

l MILLSTONE - UNIT 2 3/4 3-16 Amendment No. 63 i

I I

TABLE 3.3-3 (Continued)

=

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRU'1ENTATION p

r-MINIMUM g

TOTAL NO.

CHANf4ELS CHANNELS APPLICABLE M

FUNCTI0f4AL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

^

C F,

9.

AUXILIARY FEEDWATER

-4 l

N a.

Manual 1/ pump 1/ pump 1/pusp 1, 2, 3 1

b.

Steam Generator Level - Low 4

2 3

1, 2, 3 2

u 1

g n

t i

1 TABLE 3.3-3 (Continued)

)

With one or more channels inoperable, operation may continue l ACTION 3 provided the containment purge valves are maintained closed.

t i

i f

i J

t

.i i

f 1

r 1

I i

l l

MILLSTONE - UNIT 2 3/4 3-17 Amendment No. A4, 63 l

TABLE 3.3-4 3{

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES El 2*

ALLOWABLE I

[

FUNCTIONAL UNIT TRIP SETPOINT VALUES 5

-4 1.

SAFETY INJECTION (SIAS)

Not Applicable Not Applicable to a.

Manual (Trip Buttons) b.

Containment Pressure - High 1 5 psig 1 5 psig c.

Pressurizer Pressure - Low 1 1600 psia 1 1600 psia 2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable R

b.

Containment Pressure -- High-High 1 7 psig 1 27 psig 2

y 3.

CONTAINMENT ISOLATION (CIAS) g a.

Manual CIAS (Trip Buttons)

Not Applicable Not Appitcable b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable c.

Containment Pressure - High 1 5 psig 1 5 psig i

d.

Pressurizer Pressure - Low 1 1600 psia 1 1600 psia 4.

MAIN STEAM LINE ISOLATION Steam Generator Pressure - Low 1 500 psia 1 500 psia j

I I

~ ~ - - -

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

4 TABLE 3.3-4 (Continued)

L ENGINEERED SAFETY FEATURE ACTUATION SYSTFM INSTRUMENTATION TRIP _ VALUES ALLOWABLE TRIP VALUE VALUES

[

FUNCTIONAL UNIT a

5.

ENCLOSURE BUILDING FILTRATION (EBFAS)-

to Manual EBFAS (Trip Buttons)

Not Applicable Not Applicable a.

b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable 8

c.

Containment Pressure - liigh 1 S psig 1 5 psig d.

Pressurizer Pressure - Low 1 1600 psia 1 1600 psia 6.

CONTAl!#1ENT SUMP RECIRCULATION (SRAS)

Manual SRAS (Trip Buttons)

Not Applicable Not Applicable

{

a.

b.

Refueling Water Storage Tank - Low 48 + 18 inches above 48 + 18 inches above tanE bottom tank bottom G

7.

CONTAINMENT PURGE VALVES ISOLATION ManualCIAS(TripButtons)

Not Applicable Not Applicable a.

b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable c.

Auturnatic CIAS Actuation Logic Not Applicable Not Applicable d.

Containment Radiation - liigh R

g Gaseous Activity

< the value deteemined

< the value determined Tn accordance wiui Tn accordance with g

Specification 4.3.2.1.4 Specification 4.3.2.1.4 5

g Particulate Activity (Half Lives

< the value determired

< the value detennined greater than 8 days)

Tn accordance with Tn accordance with Specifica tion 4.3.2.1.4.

Specification 4.3.2.1.4.

/6

___1-_-

(

1 1

TABLE 3.3-4 (Continued) f 2

~

G.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAfl0N TRIP VALUES r-i

!R ALLOWADLE i

FUNCTIONAL UNIT TRIP VALUE VALUES i

i U

8.

LOSS OF POWER i

~

a.

4.16 kv Emergency Bus Undervoltage (Undervoltage relays) - level one

> 2912 volts

> 2912 valts b.

4.16 kv Emergency Bus Undervoltage

> 3700 volts with

> 3700 volts with (Undervoltage relays) - level two an 8.0 + 2.0 second an 8.0 + 2.0 second time deTay time deTay 9.

AUXILIARY FEE 0 WATER R

a.

Manual Not Appiicable Not App 1'lcable u

y b.

Steam Generator Level - Low

> 12%

> 10%

i i

o k

i I

a R

2 i

a 5

I U

i:

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITI4 TING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

Containment Pressure-High Safety Inject'on (ECCS) a.

1 0.0*/5.0**

3

1) High Pressure Safety Injection

2) Low Pressure Safety Injection 1 50.0*/5.0**

3) Charging Pumps 1 40.0*/40.0**

4) Containment Air Recirculation System 1 31,0*/ 31. 0**

b.

Containment Isolation 1 7.5 c.

Enclosure Building Filtration System 1 50.0*/50.0**

4.

Containment Pressure--High-High g

35.h*II)/35.6**II) a.

Containment Spray 1

5.

Containment Radiation-High 1 ountir.g period C

a.

Containment Purge Valves Isolation plus 7.5 6.

Steam Generator Pressure-Low a.

Main Steam Isolation 1 6.9 b.

Feedwater Isolation 1 60 7.

Refueling Water Storage Tank-Low a.

Containment Sump Recirculation 1 120 i

8.

Steam Generator Level-Low 240*/240*,(2) a.

Auxiliary Feedwater System 1

TABLE NOTATION Diesel generator starting and sequence loading delays included.

- Diesel generator starting and sequence loading delays not included.

Offsite power available.

(1) Header fill time not included.

(2) Includes 3-minute time delay.

MILLSTONE - UNIT 2 3/4 3-22 Amendment No. 58, 32, 63

I t

I TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.

Ma nual a.

S!AS Safety Injection (ECCS)

Not Applicable Containment Isolation Not Applicable Enclosure Building Filtration System Not Applicable b.

CSAS Containment Spray Not Applicable c.

CIAS Containment Isolation Not App,3 f cable d.

SRAS Containment Sump Recirculation Not Applicable e.

EBFAS Enclosure Building Filtration System Not Applicable f.

Auxiliary Feedwater Initiation Not Applicable l

2.

Pressurizer Pressure-Low a.

Safety Injection (ECCS)

1) High Pressure Safety Injection 5,30.0*/5.0**

2) Low Pressure Safety Injection 5,50.0*/5.0**

3) Charging Pumps 3,40.0*/40.0**

4) Containment Air Recirculation System 3, 31.0*/ 31. 0**

b.

Containment Isolation 3, 7. 5 c.

Enclosure Building Filtration System 5,50.0*/50.0**

MILLSTONE - UNIT 2 3/4 3-21 Amendment No. #5. 52, 53

TABLE 4.3-2

2 ENGINEERED SAFETY FEAlllRE ACTUATION SYSTEM INSTRUMENTAI10flSURVEILLANCE REQUIREMENTS x

a CilANNEL MODES IN WillCil CllANNEL CllANNEL FUNCTIONAL SURVEILLANCE M

2 FUNCTIONAL UNIT CilECK CAllBRATION TEST REQUIRfD b

1.

SAFETY INJECTION (SIAS)

-i a.

Manual (Trip Buttons)

N.A.

R N.A.

N b.

Containment Pressure - liigh S

R H

1, 2, 3 c.

Pressurizer Pressure - Low S

R M

1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Containment Pressure --

liigh - High S

R M

1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 R

3.

CONTAINMENTISOLATION(CIAS)

Manual CIAS (Trip Buttons)

N.A.

R N.A.

Y a.

O!

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Containment Pressure - liigh S

R H

1,2,3 d.

Pressurizer Pressure - Low S

R M

1, 2, 3 e.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 4.

MAIN STEAM LINE ISOLATION a.

Steam Generator Pressure - Low S R

M 1, 2, 3 b.

Automatic Actuat. ion Logic H.A.

N.A.

M(1 )

1, 2, 3 5.

ERCLOSURE BUILDING FILTRATION (EBFAS)

~

a.

Manual EBFAS (Trip Buttons)

N.A.

R N.A.

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Containment Pressure - liigh S

R H

1,2,3 d:

Pressurizer Pressure - Low S

R M

I, 2, 3 e.

Automatic Actuation Logic N.A.

N.A.

M(1 )

1, 2, 3

TABLE 4.3-2 (Continued) 2

{

ENGINEERED SAFETY FEAluRE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS I

CilANNEL MODES IN WHICH CilANNEL CliANNEL FUNCTIONAL SURVEILLANCE TUNCTIONAL UNIT CllECK CAllBRATION TEST REQUIRED M

6.

CONTAlmENT SUMP RECIRCULATION (SRAS)

N a.

Manual SRAS (Trip Buttons)

N.A.

R N.A.

b.

Refueling Water Storage Tank - Low S

R M

1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 7.

CONTAINMENT PURGE VALVES ISOLATION a.

ManualCIAS(TripButtons)

N.A.

R N.A.

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

g c.

Automatic CIAS Actuation Logic N.A.

N.A.

M(1 )

1, 2, 3 a

<p d.

Containment Radiation - liigh y

Gaseous Monitor S

R M

ALL MODES Particulate Monitor S

R M

ALL MODES 8.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage (Undervoltage relays) - level one S

R M

1, 2, 3 b.

4.16 kv Emergency Bus I

k Undervoltage (Undervoltage relays) - level two S

R M

1, 2, 3 g

k 9.

AUXILIARY FEE 0 WATER a.

Manual N.A.

N.A.

R N.A.

.o b.

Steam Generator level - Low S

R M

1, 2, 3 1

2 1

P i.

TABLE 4.7-1 3

r'~

STEAM LINE SAFETY VALVES I

8 VALVE NUMBERS LIFT SETTING (i 1%)_

ORIFICE SIZE l

4.515 in.2 a.

2-MS-246 & 2-MS-247 1000 psia i

m 4.515 in.2 b.

2-MS-242 & 2-MS-254 1005 psia 4.515 in.2 c.

2-MS-245 & 2-NS-249 1015 psia 4.515 in.2 d.

2-MS-241 & 2-MS-252 1025 psia 4.515 in.2 y

e.

2-MS-244 & 2-MS-251 1035 psia La 4.515 in.2 f.

2-MS-240 & 245-250 1045 psia 4.515 in.2 g.

2-MS-239, 2-MS 243, 1050 psia 2-MS-248 & 2-MS-253

=

a E

i

. ~. -

PLANT SYSTEMS AUXILIARY FEEDWATER PUMPS LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps shall be OPERABLE with:

a.

Two feedwater pumps capable of being powered from separate OPERABLE emergency busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILII1: tiODES 1, 2, and 3.

ACTION:

I With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered from separate OPERABLE emergency busses and one capable of being powered by an OPERABLE steam supply system) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

i

~

At least once per 31 days by:

a.

1.

Starting each pump from the control room, 2.

Verifying that:

a) Each motor driven pump develops a discharge pressure of 3,1070 psig on recirculation flow, and b) The steam turbine driven pump develops a discharge prEcsure of,1000 psig on recirculation flow.

3 MILLSTONE - UNIT 2 3/4 7-4 Amendment No. 63

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying that each pump operates for at least 15 minutes.

4 Cycling each testable, remote operated valve through at least one complete cycle.

5.

Verifying the correct position for each manual valve not locked, sealed or otherwise secured in position.

6.

Verifying the correct position for each remote operated valve.

t.

Before entering MODE 3 after a COLD SHUTDOWN of at least 30 days by completing a flow test that verifies the flow path from the condensate storage tank to the steam generators.

c.

At least once per 18 months during shutdown by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.

2.

Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each' auxiliary feedwater actuation test signal.

~

MILLSTONE - UNIT 2 3/4 7-5 Amendment No. 32, 63

PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION I

I 3.7.1.3 The condensate storage tank shall be OPERABLE with a minimum contained volume of 150,000 gallons.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With less than 150,000 gallons of water in the condensate storage tank, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

Restore the water volume to within the limit or beg in HOT a.

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or b.

Demonstrate the OPERABILITY of the fire water system as a backup supply to the auxiliary feedwater pumps and restore the condensate storage tank water volume to within its limits within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS I

4.7.1.3 The condensate storage tank shall be demonstrated OPERABLE at i

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the water level.

l t

MILLSTONE - UNIT 2 3/4 7-6

3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% (1100 psig) of its design pressure of 1000 psig during the most severe anticipated system cperational transient. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in ac.ordance with the requirements of Section III of the ASME boiler an(

Pressure Code, 1971 Edition. The total relgeving capacity'for all 1bs/hr which is 108 percent valves on all of the steam lines is 12.7x10 6 of the total secondary steam flow of 11.8x10 lbs/hr at 100% RATED THERMAL POWER.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channel s. The reactor trip setpoint reducticns are dertved on the following bases-i For two loop operation t

SP = (X) - (Y) N)- X 106.6 l

X where:

i reduced reactor trip setpoint in percent of RATED SP

=

THERMAL POWER I

maximum number of inoperable safety valves per steam V

=

line l

1 l

l l

MILLSTONE - UNIT 2 B 3/4 7-1 Amendment No. 42,61 i

l

PLANT SYSTEMS B AS E

Power Level-High Trip Setpoint for two loop operation 106.6

=

Total relieving capacity of all safety valves per X

=

steam line in lbs/ hour = 6.35 x 106 lbs/ hour Maximum relieving capacity of any one safety valve Y

=

in lbs/ hour = 7.94 x 105 lbs/ hour 3/4.7.1.2 AUXILIARY FEEDWATER PUMPS The OPERABILITY of the auxiliary feedwater pumps ensures that the 0

Reactor Coolant System can be cooled down to less than 300 F from normal operating conditions in the event of a total loss of off-site power.

Any single motor driven or steam driven pump has the reqqired j

capacity to provide sufficient feedwater flog to remove reactor decay heat and reduce the RCS temperature to < 300 F where the shutdown cooling system may be placed into operation for continued cooldown.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water fs available for cooldown of the Reactor Coolant System to less than 300 F in the event of a total loss of off-site power. The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with steam discharge to atmosphere.

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction MILLSTONE - UNIT 2 B 3/4 7-2 Amendment No. 52, 67, 63

ML20003A169

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