Text

Amend 129 to License NPF-49,modifying TSs to Relocate TS Requirements for CP Exhaust & Supply Valves & Removal of Duplicate Testing Requirements for SI Input from Engineered Safety Features
	ML20113C270
Person / Time
Site:	Millstone
Issue date:	06/27/1996
From:	Mckee P; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20113C273	List: ML20113C270; ML20113C275;
References
	NUDOCS 9607010092
	Download: ML20113C270 (15)
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@ Etcy p

UNITED STATES g

j NUCLEAR REGULATORY COMMISSION t

WASHINGTON D.C. So65NW01 i

\\.....g f

NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

QQ MET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-49 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated June 27, 1995, as supplemented July 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;

{

and i

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 1

l 9607010092 960627

)

PDR ADOCK 05000423 1

P PDR 2

l.-

a 4

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l

and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:

j (2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised 1

through Amendment No.129

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, i

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION h.

Phillip F. McKee r tor liertheast Utilities Project Directorate Division of Reactor Projects - I/II j

Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 27, 1996 4

ATTACHMENT TO LICENSE AMENDMENT NO. 129 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 3-3 3/4 3-3 3/4 3-11 3/4 3-11 3/4 3-19 3/4 3-19 3/4 3-24 3/4 3-24 3/4 3-25 3/4 3-25 3/4 3-27 3/4 3-27 3/4 3-37 3/4 3-37 3/4 3-41 3/4 3-41 3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 8 3/4 3-3 B 3/4 3-3

)

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION f

f w

E MINIMUM m

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION EQ

12. Rea: tor Coolant Flow--Low a.

Single Loop (Above P-8) 3/ loop in 2/ loop in 2/ loop in 1

6 w

each oper-any oper-each oper-l ating loop ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop in 2/ loop in 2/ loop 1

6 below P-8) each oper-two oper-each oper-t ating loop ating loops ating loop

13. Steam Generator Water 4/sta. gen.

2/stm. gen.

3/sta. gen.

1, 2 6 (1) l Level--Low-Low in each oper-in any oper-each oper-ating sim.

ating stm.

w1 gen.

gen.

l w

4,

14. Low Shaft Speed--Reactor l

Coolant Pumps a.

Four loop operation 4-1/ pump 2

3 1**

6 b.

Three loop operation 3-1/ pump 2

2 1**

6

15. Turbine Trip a.

Low Fluid Oil Pressure 3

2 2

1***

12 b.

Turbine Stop Valve Closure 4

4 4

1***

6 t

Deleted g 16.

"g. 17. Reactor Trip System Interlocks a

a.

Intermediate Range i

5 Neutron Flux, P-6 2

1 2

2H 8

j z

?

b.

Low Power Reactor Trips Block, P-7 w5 P-10 Input 4

2 3

1 8

N or P-13 Input 2

1 2

1 8

iG

^

If r

o r-h TABLE 4.3-1 (Continued)

E REACTOR TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIRENENTS m

TRIP j

g ANALOG ACTUATING NODES FOR t

CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST 15 REQUIRED l

13. Steam Generator Water Level--

S R

Q(18)

N.A.

1, 2 Low-Low

14. Low Shaft Speed - Reactor N.A.

R(13)

Q N.A.

N.A.

1 i

Coolant Pumps i

15. Turbine Trip a.

Low Fluid Oil Pressure N.A.

R N.A.

S/U(1,10)****N.A.

I b.

Turbine Stop Valve N.A.

R N.A.

S/U(1,10)****N.A.

1 l

Closure j

g

[

16. Deleted 0

17. Reactor Trip System Interlocks a.

Intennediate Range Neutron Flux, P-6 N.A.

R(4)

R N.A.

N.A.

2**

b.

Low Power Reactor P-7 N.A.

R(4)

R N.A.

N.A.

I Trips Block, Neutron Power Range r

c.

P-8 N.A.

R(4)

R N.A.

N.A.

I Flux, Range Neutron d.

Power P-9 N.A.

R(4)

R N.A.

N.A.

I Flux, Ran Power ux P-10 N.A.

R(4)

R N.A.

N.A.

1, 2 f

P e.

NeutronF$e E

Pressure,$uiseChamber Turbine I f.

k

-13 N.A.

R R

N.A.

I E

F j

D.

=

h

=

~.

l 4

TABLE 3.3-3 (Continued) i ENGIMMRED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION G

-4 E

MINIMUM i

TOTAL NO.

CHANNELS CHANNELS APPLICA8LE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION l

E A

3.

Containment Isolation (Continued) w

3) Containment 4

2 3

1, 2, 3, 4 17 Pressure--High-3 i

c.

Purge Isolation 2

1 2

5, 6*

26 4.

Steam Line Isolation l

a.

Manual Initiation w1

1) Individual 1/ steam line 1/ steam line 1/ operating 1, 2, 3, 4 24 w

steam line

2) System 2

1 2

1, 2, 3, 4 23 b.

Automatic Actuation 2

1 2

1, 2, 3, 4 22 Logic and Actuation Relays c.

Containment Pressure--

3 2

2 1, 2, 3, 4 20 E.

High-2 5

E d.

Steam Line Pressure--

3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

20

)

z Low in each in any in each operating operating operating g

1oop 1 cop 1 cop-t w

e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/ steam line 3****

20 l

7 Negative Rate--High in each in any in each i

g operating operating operating loop loop loop i

G e

I TABLE 3.3-3 (Continued) 1 IEMOTAT10M

]

1

]

The Steamline Isolation Logic and Safety Injection Logic for this trip l

function may be blocked in this MODE below the P-11 (Pressurizer l

Pressure Interlock) Setpoint.

j Trip function automatically blocked above P-ll and may be blocked below l

P-Il when Safety Injection on low steam line pressure is not blocked.

During core alterations or movement of irradiated fuel within the containment. The provisions of Specification 3.0.3 are not applicable.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to i

OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, j

provided the other channel is OPERABLE.

ACTION 15 - (not used).

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of i

the next required ANALOG CHANNEL OPERATIONAL TEST provided 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 .

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met.

One additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 18 - With less than the Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation.

ACTION 19 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, 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 at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MILLSTONE - UNIT 3 3/43-24 Amendment No. 57, 77, 77, 129 0370

TABLE 3.3-3 (Continued)

ACTION STATENENTS (Continued)

ACTION 20 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

the Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than the 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 at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 - With the number of OPERABLE channels one less than the 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least. HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 26 - With less than the Minimum Channels OPERABLE requirement, the containment purge and exhaust valves shall be maintained closed.

Fuel movement and CORE ALTERATIONS may continue.

The contai. ment radiation monitoring channels required for containment arek purge and exhaust isolation are not required to be OPERABLE during the performance of Type A containment leakage rate tests.

MILLSTONE - UNIT 3 3/43-25 Amendment No. 79, 129 0379 c

,-4,,

v m

TABLE 3.3-4 h

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS G

SENSOR k

TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE fTA)

I (S)

TRIP SETPOINT ALLOWABLE VALUE 3.

Containment Isolation (Continued)

2) Automatic Actuation Logic N.A.

N.A.

and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

b. Phase "B" Isolation

1) Nanual Initiation N.A.

N.A.

R

2) Automatic Actuation N.A.

N.A.

Y Logic and Actuation O

Relays

3) Containment Pressure--

3.3 1.01 1.75 5 8.0 psig i 8.8 psig High-3

c. Purge Isolation N.A N.A N.A.

s 1 R/h 5 1 R/h l

4.

Steam Line Isolation

a. Manual Initiation N.A.

N.A.

k

b. Automatic Actuation Logic N.A.

N.A.

3 and Actuation Relays

c. Containment Pressure--High-2 3.3 1.01 1.75 1 3.0 psig s 3.8 psig

d. Steam Line Pressure--Low 17.7 15.6 2.2 2 658.6 psig*

1 648.3 psig*

4

e. Steam Line Pressure -

5.0 0.5 0

s 100 psi /s**

s 122.7 psi /s**

Negative Rate--High

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION og;:

SURVEILLANCE RE0UIRENENTS r-U TRIP E

ANALOG ACTUATING fiDDES CHANNEL DEVICE NASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

! FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IESI TEST IS REGUIRED

{

.a w

3. Containment Isolation

a. Phase "A" Isolation

1) Nanual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) Automatic Actuation N.A.

N.A.

N(1)

Q 1, 2, 3, 4 Logic and Actuation Relays

3) Safety Injection See Item 1. above for di Safety Injection Surveillance Requirements, w

k

b. Phase "B" Isolation

1) Nanual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

{

2) Automatic Actuation N.A.

N.A.

N(1)

Q 1, 2, 3, 4 Logic Actuation s(

Relays a"

3) Containment S

R Q

N.A.

1, 2, 3, 4 f

Pressure-High-3 y

c. Purge Isolation S

R Q

N.A.

5, 6#

l 3

4. Steam Line Isolation y

a. Nanual Initiation

1) Individual N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

}

2) System N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

_m

--_-__.-.__._.__.--5.

--m.__m' m____u_.._-.__a__._

_wszmru_

m a____.kr.#~_.a=-a.-

-L._.-_aa.._a u.

+u.v__.Am

l.-

TABLE 4.3-2 (Continued)

TABLE NOTATION (1)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2)

This surveillance may be performed continuously by the emergency generator load sequencer auto test system as long as the EGLS auto test system is demonstrated operable by the performance of an ACTUATION LOGIC TEST at liast once per 92 days.

(3)

On a monthly basis, a loss of voltage condition will be initiated at each undervoltage monitoring relay to verify individual relay operation.

Setpoint verification and actuation of the associated logic and alarm relays will be performed as part of the channel calibration required once per 18 months.

f During core alterations or movement of irradiated fuel within the containment. The provisions of Specification 3.0.3 are not applicable.

MILLSTONE - UNIT 3 3/4 3-41 Amendment No. JJ, 7J 7), 7pp,129 eies

i TABLE 3.3 6 RADIATION N0NITORING INSTRUNENTATION FOR PLANT OPERATIONS Ga l

MINIMUM t

CHANNELS CHANNCLS APPLICABLE ALARM / TRIP l

FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT 101191(

E U

1.

Containment u

a. Deleted j

b. RCS Leakage Detection

1) Particulate Radioactivity N.A.

I 1, 2, 3, 4 N.A.

29

2) Gaseous Radioactivity N.A.

I 1, 2, 3, 4 N.A.

29 2.

Fuel Storage Pool Area Monitors 1 IS mR/h 28

a. Radiation Level 1

2 Y

0 5a Ea E

M

TABLE 3.3-6 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas.

ACTION STATEMENTS ACTION 27 -

Not used.

ACTION 28 -

With less than the Minimum Channels OPERABLE requirement, fuel movement may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area. Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 29 -

With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, comply with the. ACTION requirements of Specification 3.4.6.1.

t NILLSTONE - UNIT 3 3/4 3-44 AmendmentNo.(J.129 asu

TABLE 4.3-3 l5 RADIATION MONITORING INSTRUMENTATION FOR PLANT

{

OPERATI 9f(S.. SURVEILLANCE _ REQUIREMENTS E

ANALOG CHANNEL MODES FOR WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED w

1.

Containment a.

Deleted l

b.

RCS Leakage Detection

1) Particulate Radio-S R

Q 1, 2, 3, 4 activity

2) Gaseous Radioactiv;ty S

R Q

1, 2, 3, 4 2.

Fuel Storage Pool Area Monitors Yg a.

Radiation Level S

R Q

TABLE NOTATIONS g

With fuel in the fuel storage pool area.

5 W

?

G w

J

INSTRWENTATION BASES REACTOR TRIP SYSTEM INSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The Engineered Safety Features Actuation System interlocks perform the following functions:

)

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valvesonT.,IveswhichwereclosedbyaSafetyInjectionorHigh below Setpoint, prevents the opening of the main feedwater va Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure and low steam line pressure. On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pressure and low steam line pressure.

P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the Steam Dump System. On decreasing reactor coolant loop temperature, P-12 automatically removes the s

arming signal from the Steam Dump System.

P-14 On increasing steam generator water level, P-14 automatically trips all feedwater isolation valves, main feed pumps and main turbine, and inhibits feedwater control valve modulation.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERA 8ILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetenmined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms.

NILLSTONE - UNIT 3 B 3/4 3-3 Amendment No.129 0385 l

_

ML20113C270

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