Text

Amend 1 to License NPF-56,changing Tech Spec Setpoints for Pressurizer Pressure,Pressurizer Water Level & Steam Generator Water Level Channels as Result of Replacing Veritak/Tobar Transmitters W/Rosemount Transmitters
	ML20154Q887
Person / Time
Site:	Seabrook
Issue date:	09/27/1988
From:	Wessman R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20154Q757	List: ML20154Q754; ML20154Q887; ML20154Q988;
References
	NUDOCS 8810040094
	Download: ML20154Q887 (19)
	v • d • e

.

seagep

/ o

', UNITE 0 STATES

['

3 m i t

NUCLF AR REGULATORY COMMISSION WASHINGTON D. C. 20666

\,*...a/

PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE. ET AL.*

DOCKET NO. 5C.443 SEABROOK STATION, UNIT 1 AMENDMENT TO FACI'.iTY OPERATING LICENSE Amendment No, i Lii;ense No. NPF.56

1. The Nuclear Regulatory Connission (the Connission) has found that A. The application for amendment by Public Service Company of New '

Hampshire (PSNH), as agent and representative of the utilities listed below (and hereafter the utilities listed below including PSNH collectively referred to as licensees) dated July 8, 1988 and supplemented by its August 8, 1988 submittal complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFP. Chapter I; B. The facility will operate in conforwity with the application, the provisions of the Act, and the rules and regulations of the Connission; C. There it reasonable assurance (i) that the activities authorized by this ameti6 ment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D. The issuance of this amend.nent will not be inimical to the cormun deferise and security or to the health and safety cf the public; and E. The issuance of this amendruent is in accordance with 10 CFR Part 51 of the Consission's regulations and all applicable requireents have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arnenament, and paragraph 2.C.(2) of Facility Operating License No. NPF.56 is hereby amended to read as follows:

Publ5c Service Company of New Parpshire is authorized to act as agent for ths: Canal Electric Lompany. The Connecticut Light and Power Company, EUA Power Corporation, Hudson Light & Power Company Massachusetts Municipal Wholesale Electric Company Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Lighting Plant, the United Illuminating Corpany, and Vermont Electric Generation end i Transmissier. Cooperative, Inc., and has exclusive responsibility and cantrol over the chysical construction, oparation and r.aintenance of the facility.

881004oo94 ggo997 hDR ADOCK 05000443 PNU

t i

.?.

6 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1. are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REG'lLATORY COMMISSION

, T N.

Ric:ard H. Wessman Director Project Directorate 1-3 I Division of Reactor Projects 1/!!

l

Attachment:

Changes to the Technical Specifications l Date of Issuance: September 27, 1988 I :

1 !

i

[

i !

f l l L

(

t i

t

ATTACHMENT TO LICENSE AMENDMENT NO.1 FACILITY OPERATING LICENSE NO. NPF-56 DOCKET NO. 50-443 Revise Appendix A Technical Specificatiens by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area j of change. The corresponding overleaf.pages are provided to maintain document completeness.

Remove Insert

2-4 2-4 1 2-5 25 i

3/4 3 24 3/4 3-24 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 4-3 3/4 4-3 3/4 4-5 3/4 4-5

. 3/A 4 6 3/4 4-6

! 3/4 6-12 3/4 6-12 i

j 4

i j

I

l 1

SAFETY LIMITS AND LIMITING SAFETY SYSTFM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: As shown for each channel in Table 3.3-1.

ACTION:

a. With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value,

b. With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the v&lue shown in the Allowable Value column of Table 2.2-1, either:

1. Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that Equation 2.2-1 was satisfied for the affected channel, or

2. Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.

Equation 2.2-1 Z + R + 51 TA Where:

Z = Tne value from Column Z of Table 2.2-1 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value from Column 5 (Sentor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.

SEAER00A UNIT 1 2-3

l t

l l 'i

, 3 a -m TABLE 2.2-1

, d h

=

REACTOR TRIP SYSTEN INSTRUENTAIION TRIP SETPOIN!5 l%

?

z h SE450R

, TOTAL Ek20N e IUNCTIONAL UNIT ALLOWANCE ITA) Z_ (5) TRIP SETPOINT ALLOWABLE VALUE

$ 1. Manual Reactor Trip N.A. N.A. M. A. N.A. N.A.

2. Power Range Neutron Flux

a. High Setpoint 7. 5 4.56 0 110'A of RTP* $111.1% of RTP"

b. Low setpoint 8.3 4.56 0 125% of RTP* 127.13 of RTP*

3. Power Range, Neutron Flux, 1. 6 0.5 0 15% of RTP* with $6.3% af RTP" with High Positive Rate a time constant a time constant

>2 seconds 32 seconds y 4. Power Range. Eeutron Flux, 1.6 0.5 0 15% of RTP* with 16.'4 of RTP" with

. High Negative Rater a time constant a time constant 12 seconds 32 seconds ,

5. Intermediate R m 17.0 8.41 0 125% of RTP* 131.1% of RTP*

Neutron Flux

~

6. Source Range, Neutron Flux 17.0 10.01 0 110' cps 11.6 x IOS cps

7. Overtemperature AT 6.5 3.31 1.04** See Note 1 See Note 2

+0.47**

8. Overpower AT 4.8 1.43 0.12 See Note 3 See Note 4

9. Pressurizer Pressure - Low 3.12 0.86 0.99 31945 psig 31,931 psig

10. Pressurizer Pressure - High 3.12 1.00 0.99 $2385 psig 12,396 psig

RTP = RATED THEIMAL POWER

- The sensor error for I,,g is 1.04 and the sensor error for Pressurizer Pressure is 0.47. "As measured" sensor errors may be used in lieu of either or both of these values, which then must be summed to deter-eine the overtemperature AT total channel value for 5. - *

?i . '

3 , TA8tf 2.2-1 (Continued) kh aB REACIOR TRIP SYSTEM INSTRtMENTATION TRIP SETPOINis z g SENSOR .

TOTAL ERROR b[ TUNCTIONAL UNIT ALLOWANCE (IA) Z (5) TRIP SE1 POINT ALLOWABLE VALUE h 11. Pressurizer Water Level - High 8.0 4.20 0.84 $92% of instrument 193.75% of instrument l c span span

12. Reactor Coolant flow - Low 2.5 1.87 0.6 >90% of loop >89.4% of loop design flow

3esign flow *

13. Steam Generator Water 14.0 12.53 0.55 >14.0% of narrow >12.6% of narrow Level Low - Low range instrument range instrument l span span

14. Urdervoltage - Eeactor 15.0 1.39 0 >10,200 volts 23,822 velts Coolant Pimps y 15. Underfrecuency - Reactor 2.9 0 0 >55.5 Hz >55.3 Hz m' Coolant Pumps

16. Turbine Trip

a. Low fluid Oil Pressure N.A. N.A. M.A. >500 psig >450 psig

b. Turbine Stop Velve M.A. M.A. M.A. >l% open >1% open Closure

17. Safety Injection input N.A. N.A. N.A. N.A. M.A.

from ESF

Loop design flow = 95,700 gpa 1

_=__ --- _ . _ .. _ _ _ __ _ _ _ _ _ - _ . . . - _ _ _ _ . __- .

i

v. 1ABLE 2.2-1 (Continued) j Rf ACTOR IRIP SYSI[N INSTRUNfCTATION TRIP SETP0l**is n

8

^ SENSOR TOTAL [RROR IUNCTIONAL UNIT Att0WANCE (TA) f (5) TRIP SIIPolNT All0WABLE VALUE A

18. Reactor Irip System Interlocks e

a. Intermediate Range N.A. N.A. M.A. ll x 10 88 amp 36 x 10 88 amp Neutron fIun, P-6 4

b. Low Power Reactor Trips l Block, P-7

1) P-10 input N.A. N.A. N.A. $10% of RTP* <12.1% of RIP

j

, 2) P-13 input N.A. N.A. M.A. <10E RIP

Iurbine <12.3% RIP

Iurbine u Impulse Pressure Impcise Pressure j J. Equivalent Equivalent i c. Power Range Neutron M.A. N.A. M.A. $50% of RIP * $52.1% of RIP

Ilux, P-8

d. Power Range Neutron M.A. N.A. M.A. $20E of RIP

flux, P-9

$22.1% of RIP

s

c. Power Range Neutron N.A. N.A. N.A 310E of RTP" flux, P-10 37.9% of RIP *

f. Turbine Impulse Chamber M.A. N.A. M.A. <10E RIP

Turbine <12.31 EIP* Iurbine .

Pressure, F-13 lopulse Pressure lapulse Pressure Equivalent Equivalent

19. Reactor irip Breakers N.A. N.A. M.A N.A. N.A.

l 20. Automatic Trip and Interlock N.A. N.A. M.A. M.A. N.A.

Logic i

RTP = RATED THlHMAL POWER J

S w.s--ye - -- g -

-, > , - -w -- - -

, e -,e - _ . , --

-,, _ , , r -, , - -

r,j, e I

1 TABit 3.3-3 (Continued) t l ACTION STATEMENTS (Continued) 1

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and D. The Minimum Channels ~ OPERABLE requirement is met; however, i one additional channel may be bypastert for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for :.trveillance testing of other channels per Specification 4.3.2.1.

l A fl0N 19 W'tm less than the Minimum Number of Channels OPERA 8LE, within I

1 iiour determine by observation of the associated permissive annunciator itindow(s) that the interlock is in its required l stati for the existing plant condition, or apply Specification l 3.0 3.

ACTION 20 - Wfth the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAN08Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months end in at least HOT SHUTOOWN within the following S hours; however, one channel may be bypassed 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 provided the otner chaanel is OPERA 8LE.

ACTION 21 - With the number of OPERA 8LE channels one less than the Total Nuecer of Channels, restore the inoperable channel to OPERABLE states wit.iin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 heurs and in at least HOT SHUTOOWN within the following C host,s.

l ACTION 22 - With the nuetser of OPERA 8LE channels one less than the Minimum Chane.cis CPERA8LE requirement, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; Nwever, one channel say be byoassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillonce testing per Specification 4.3.2.1 provided the other tMrnel is OPERA 8LE.

ACTION 23 - With the tweer of OPERA 8LE channels one less than the 1otal 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 declare the associated valve inoper-able anti take the ACTION required by Specification 3.7.1.5.

SEABROOK - UNIT 1 3/4 3 23

'I g, TABLE 3.3-4 39 3g ENGINEERED SAFEIY FEATURES ACTUATION SYSTEN INSTRUENTATION TRIP SEIPOINIS 8

E" o SENSOR g TOTAL ERROR q FUNCTIONAL UNil ALLOW NCE (TA) Z_ (5) TRIP SEIPOINI ALLOWABLE VALUE c-

1. Safety injection (a, actor Trip, Feessater Isolation, Start Diesel Generators Phase "A" Isolation, Containment Ventilation Isolation, and Emergency Feessater, Service Wter to Secondary Component Cooling Wier Isolation CSA Emergency Fan / Filter Actuation,

, and Latching Relay).

2

, a. h nual Initiation N.A. N.A. N.A. N.A. N.A.

b. Automatic Actuation Logic M.A. M.A. N.A. N.A. N.A.

c. Containment Pressure--Hi-1 4.2 0.71 1.67 1 4.3 psig 1 5.3 psig

d. Pressurizer Pressure--Low 15.0 12.91 0.99 3 1865 psig 3 1852 psig l

e. Steam Line Pressure--Low 13.1 10.71 1.63 1 585 psig 1 568 psig"

2. Conttinment Spray l

a. hnual Initiation N . f. M.A. N.A. N.A. M.A.

l l b. Automatic Actuation Logic M.A. M.A. M.A. N.A. N.A.

l and Actuation Relays l

c. Containment Pressure--Hi-3 3.0 0.71 1.67 $ 18.0 psig i 18.7 psig l _ _ _ _ _ _ _ . . _ - _ _

IABLE 3.3-4 (Continued) h T,

iNGINEI R10 SAILIY f( Af tNtl5 ACIIJAIION SY$1IN IN51RtmlMIAIION IRIP SIII'GINIS 8

SENSOR 101At [kNOR lijNCI!ONAt tmli At10WANCE (IA) / (5) 1 RIP SilPOINI Att0WABLE VALUt O 3. Contaiseent Isolation e

a. l'hase "A" Isolation I) k nual Initiation M.A. N.A. N.A. M.A. N.A.

2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

and Actuation Nelays

3) Safety injection See Ites 1. above for all Safety injection Trip 5etpoints and Allowatele Values.

%. 13 Phase "B" Isolation s

1) Manual Initiation N.A. N.A. N.A. N.A. N.A. .

{ 1

2) Automatic Actuation M.A. N.A. N.A. N.A. N.A. f 1ogic and Actuation ,

Nelays

3) Containment Pressure-- 3.0 0.11 1.67 1 13.0 psig < 18.1 psig i Hi-3

c. Containment Ventilation Isolation

1) k nual Initiation N.A. N.A. M.A. N.A. N.A.

l 2) Automatic Actuation N.A. N.A. N.A. N.A. N.A.

l logic and Actuation Relays l

l

3) Safety injection See 'Ites 1. alsove for all Safety Injection Trip Setpoints and 1 Allowatste Values.

4) C4,ntainment On t ine Purge N.A. N.A. N.A. <2x l' . A .

Radioactivity-High 84ckgrouent l

l l

l

'I e

g.C TABLE 3.3-4 (Centinued) 3, g ENGIN((R(D SAFETY Ff ATUR[s AC1UATION SYST[N INSTRUBENTATION TRIP SEIPOINTS

.e 8 P^ o SEN50s

- TOTAL ERROR g

FuteCT10NAL UNII ALLOWANCE (TA) Z_ (5) ! RIP SETP0 INT Att0WASLE VALUE g 4. Steam Line Isolatten

a. Ma..ual Initiation (System) ::. A. M.A. N.A. N.A. N.A.

b. Automatic Actuatfan Logic M.A. N.A. N.A. N.A. N.A.

and Actuation Relays

c. Containment Pressure--Ni-2 5.2 0.71 1.67 14.3 psig $5.3 psig y d. Steam Line Pressure--Low 13.1 10.71 1.63 1585 asig 1568 psig*

1 3.0 0.5 0 1100 psi 1123 psi"* l

, c. Steam Generator Pressure -

( 4 Negative Rate--Migh l

l 5. Turbine Trip l

a. Automatic Actuation Ltgic N.A. N.A. N.A. N.A. M.A.

l Actuation Relays

b. Steam Generater Water 4.0 2.24 0_55 -<36.5 of <87.7% of narrow l !

Level--Migh-High (P-14) nerrow range fange lastrument I instrement span.

SP84.

6. Feedwater Isolation

a. Steam Generator Water 4.0 2.24 0.55 <86.E of <87.71 of narrow l Level--Ni-Hi-(P-14) harrow range range instrument instrement span.

Span.

l

b. 4.6 1.12 1.38 1564*f 1561.2*f Low RC5 1 ,,g Coincident with Reac;sr Trip

c. Safety Injection M.A. N.A. N.A. N.A. N.A. ,

+

s

, TABLE 3.3-4 (Continued)

= (NGINEERed SAf[TY f EATURES ACluATION SYSTEN INSTRUIENTATION TRIP SEIP0lNIS o

N SENSOR

~

e TOTAL ERROR -

FUNCil0NAL UNIT Att0WANCE (TA) Z (5) TRIP SEIP0lNI Att0WA8tf VALUE

] 1. [mergency fee h ter

a. Manual Initiation (1) h ter drivec pump N.A. N.A. N.A. N.A. N.A.

(2) Turteine driven pump N.A. M.A. N.A. N.A. N.A.

b. Automatir. Actuation Logic N.A. N.A. M.A. M.A. N.A.

and Actuation Relays w c. Steam Generator Water 14.0 12.53 0.55 ~> 14.07,of > 12.6% of narrow l 2 Lw el--Low-tow narrow range range instrument w Start hter-Driven Pump instrument sp w.

3 and Start lurbine-Driven span.

Pump

d. Safety Injection See Itee 1. above for all Safety Injection Trip 5etpoints and Star?, htor-Driven Pump Allowable Values.

and Turbine-Driven Pump

e. toss-of-Offsite Power See Ites 9. for toss-of-Offsite Power Setpoints and AllM1e Values.

Start Motor-Driven Pump and Turbine-Driven Pamp

8. Automatic Switchover to Containment Sump

a. Automatic Actuation Logic N.A. M.A. N.A. M.A. M.A.

and Actuation Relays

b. NWST tevel--tow-tow 2.75 1. 0 1.8 ->1/2.525 gals. >121.609 gals.

Coincident With Safety Injection See Ites 1. above for all Safety Injection Trip Setpoints and Allowable Values.

'l 3 , TABLE 3.3-4 (Continued)

't O

% ENGINEERED SAFETY FEATURES ACTUATIJN SYSTEN INSTRuffMTATION TRIP SETPolNTS 8

^

6 SENSOR TOTAL ERROR g TUNCTIONAL UNil Att0WANCE (TA) 2 (5) TRIP SETPOINT ALLOWABLE VALUE O

g 9. loss of Power (Start Emergency feeesater)

a. 4.16 kV Sus E5 and E6 N.A. N.A. M.A. > 2975 > 2S08 volts Loss of Voltage volts with Gith a $ 1.315 a < 1.20 second time second time delay.

delay.

b. 4.16 kV Sus E5 and [6 N.A. N.A. M.A. > 3933 volts > 3902 volts o Degraded Voltage Gith a $ 10 Gith a $ 10.%

1 second time second time o delay. delay.

4 Coincident with:

Safety Injection See Item 1. above for all Safety Injection Trip 5etpoints and Allowable Values.

10. Engineered Safety Features Actuation System Interlocks

a. Pressurizer Pressure, P-11 N.A. N.A. N.A. $ 1950 psig $ 1964 psig j

b. Reactor Trip, P-4 N.A. M.A. N.A. N.A. N.A.

c. Steam Generator Water Level, see Itee 5. above for all Steam Generator Water Level Trip P-14 Setpoints and Allowable Values.

e s

REACTOR COOLANT SYSTEM REAC10R COOL. ANT L,00PS AND COOLANT CIRCULATION HOT STANOGY SURVEILLAFCE REQUIREMENTS _.

4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERASLE once per 7 days by verifying '

correct breaker alignments and indicated power availability.

4.4.1.2.2 The required steam generators shall be determined OPERA 4LE by verify-ing secondary side water level to be greater than or equal to 145 at least once l per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4 1.2.3 The required reactor coolant loops shall be verified in operation ;

and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ~

1 1 ,

l I

1 i

i I !

l i

f i

i

)

5EABR00K UNIT 1 3/4 4 3 t A ent ent No I l

r t

i REACTOR COOLANT SYST(M REACTOR COOLANT t,00PS AND C001, ANT CIRCULATION HOT $ HUT 00wN ;

l LIMIT!NG CONDITION FOR OPERATION 3,4.1.3 At least two of the loops listed below shall be OPERA 8LE and at least !

one of these loops shall be in operation:* [

4. Reactor Coolant Loop A and its associated steam generator and l reactor coolant pump.** l D.

Reactor Coolant Loop B and its associated steam generator and ,

reactor coolant pump.** f

c. Reactor Coolant Loop C and its associated steam generator and f reactor coolant pump.** i

d. Reactor coolant Loop D and its associated steam generator and !

reactor coolant pump.** (

e. RHR Loop A, and ;

f. RHR l. cop B.

i APPLICABILITY: MODE 4 ACf!0N:

a. With less than the above required loops OPERA 4LE, immediately (

initiate corrective action to return the required loops to CPERAILE !

I i

ststus as soon as possible; if the remaining CPERASLE loop is an RHR loop. be in COLO $HUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

]

1 3. With no loop in operation, suspend all operations involving a reduc- !

t ton in boron concentration of the Reactor Coolant System and !

J inmediately initiate corrective action to return the required loop {

to operaG on. .

l r

I

M) reactor coolant pumps and RHR pumps may be doenergized for up to I hour i j provided: (1) no operations are permitteo that would cause dilution of the l 1

Reactor Coolant System boran concentration end (2) core outlet temperature i is maintained at least 10'F below saturation temperature, i

"A reactor coolant, pump shall not be started unless the secondary water temperature of each steam generator is less than 60'F above each of the !

9

Reactor Coolant Systes cold-leg temperatures. ,

a .

SEAbt00K - t'N!T 1 3/4 4 4 l i

4 REACTOR COOLANT SYSTEM

, REACTOR COOLANT LOOPS AND COOLANT CIRCULATION HOT SHUTDOWN

$URVE!LLANCE REQUIREMENTS 4.4.1.3.1 The required reactor coolant pump (s), if not in operation, shall be determined OPERAILE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generator (s) shall be determined OPERA 8LE by verifying secondary-side water level to be greater than or equal to 144 at l 1 east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.3.3 At least one reactor coolant or RHR loop shall be ytrified in operatten and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l r

l i

SEABROCK - UNIT 1 3/4 4 5 i i

8. enc ent No. 1

, l REACTOR C0OLANT SYSTEN REACTOR COOLANT LOOPS ANO COOLANT CIRCULATION COLO SHUTDOWN - LOOPS FILLED LIMITING CON 0! TION FOR OPERATION 3.4.1.4.1 At least one residual heat removal (RHR) loop shall be OPERA 8LE and in operation *, and either:

a. One additional RHR loop shall be OPERA 8LE**, or

b. The secondary side water level of at least two steam generators shall be greater than 14%. l APPLICA81LITY: MODE 5 with reactor coolant loops filled ***.

ACTION:

a. With one of the RHR loops inoperable and with less than the required steam generator water level, immediate) initiate corrective action toreturntheinoperableRURlooptoOPfRA8LEstatusorrestorethe required steam generator water level as soon as possible,

b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and ;

issnediately initiate corrective action to return the required RHR loop to operation.

I

$URVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The RHR pump may be deenergized for up to I hour provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant Systee boron concentratien and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

- 0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other RHR loop is OPERABLE and in operation.

- - A reactor coolant pump shall not be started unless the secondary water temperature of each ste'an generator is less than 50*F above each of the Reactor Coolant System cold leg temperatures.

SEABROCK UNIT 1 3/4 4 6 A,eneent No. 1

i .

l CONTAINMENT SYSTEMS i PRIMARY CONTAINMENT CONTAINMENT VESSEL STRUCTURAL INTEGR!TY LIMITING CON 0! TION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6. '

APPLICABILITY: MODE $ 1, 2, 3, and 4.

ACTION: l i

With the structural integrity of the containment vessel not conforcing to the ;

above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVE!LLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined I during the shutdown for each Type A containment leakage rate test (reference ,

Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior totheTypeAcontainmentleakageratetesttoverifynoapparentchangesin ,

appearance of the surfaces or other abnormal degradation. Any abnorma degrada-tion of the containment vessel detected during the above required inspections shall be reported to the Commission in a $pecial Report pursuant to $pecift- f cation 6.8.2 within 15 days. ,

I

[

i I

L I

I

$EABR00K. - UNIT 1 3/4 6 11

5 CONTAl MENT SYSTEMS PRIMARY CONTA!NMENT CONTAINMENT VENTILATION SYSTEM LIMITING CON 0! TION FOR OPERATION _

3.6.1.7 Each containment purge supply and exhaust isolation valve shall be OPERA 8LE and:

a. Each 36 inch containment shutdown purge supply and exhaust isolation valve shall be closed and locked closed, and

b. The 8 inch containe,ent purge supply and exhaust isolation valve (s) shall be sealed closed except when open for purge systee operation for pressure control; for ALARA, respirable, and air quality consider-ations to facilitate personnel entry; and for surveillance tests that require the valve (s) to be opan.

APPLICABILITY: MODES 1, 2, 3 and 4.

l ACTION:

a. With a 36-inch containment purge supply or exhaust isolation valve open or not locked closed, close and lock closed that valve or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , othe Nise be in at least HOT STAN0tY within the next G hours and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With one or more of the 8 inch containment purge supply or exhaust isolation valves open for reasons other than given in Specifica- t tion 3.6.1.7.b above, close the open 8 inch valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months otherwise be in at least HOT STAMORY withinthenext6 hours,andInCOLO$HUTDOWNwithinthefollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

c. With one or more containment purge suoply or exhaust isolation valves having a measured leakaga rate in excess of the limits of Specifications 4.6.1.7.2 or 4.6.1.7.3 restore the inoperable valve (s) to OPERA 8LE datus or isolate the affected penetration (s) so that the measured leakage rate does not exceed the limits of Specifications 4.6.1.7.2 or 4.6.1.7.3 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and close the purge supply if the af fected penetration is the exhaust penetration, othemise be in at least HOT STAMOGY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHL'TDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SEABROCK UNIT 1 3/4 6 12 l Vent ent 'io. 1 l

l

_ ____- _____- ____ _ J

ML20154Q887

Text

Attachment:

Navigation menu

Search