ML20126F899

Amend 167 to License DPR-65,adding High Containment Pressure Signal as Input to Main Steam Isolation & Reducing Feed Isolation Portion of Msi from 60 to 14

ML20126F899
Person / Time
Site:	Millstone
Issue date:	12/23/1992
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20126F901	List: ML20126F899 ML20126F906 ML20126F911
References
DPR-65-A-167 NUDOCS 9212310192
Download: ML20126F899 (11)

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UNITED STATES -

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NUCLEAR REGULATORY COMMISSION =

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NORTHEAST NUCLEAR' ENERGY COMPANY THE CONNECTICUT LIGHT AND' POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC' COMPANY-DOCKET NO. 50-335 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT-TO FACILITY OPERATING-LICENSE-Amendm'ent No.-167:

License No. DPR-65

?

1.

The Nuclear Regulatory Commission (the Commission) has foundithat:

A.

The application for amendment by Northeast. Nuclear Energy? company,_

et al. -(the licensee), dated 0ctober 28, 1992,'as sup)lemented November 20, 1992,-and December 4, 1992, complies wit tthe standards--

and requirements of the-Atomic Energy ' Act of 1954,- as amendedT(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 the4 Commission; C.

There is reasonable assuranceJ(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; D.

The issuance of this amendment will not' be-inimical to the-common Ldefense 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.

f 9212310192 921523 PDR. ADOCK 05000336 J: P RP.DR.-

c..

. 2.

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.167, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Direct P ject Directorate I 4 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 23, 1992

. L.:.,

e ATTACHMENT TO LICENSE AMENDMENT NO.167 FACILITY OPERATING llCENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Appendix' A Technical-Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

Remove Insert 3/4 3-13 3/4 3-13 3/4 3-18 3/4 3-18 3/4 3-21' 3/4 3-21 3/4.3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 8-2 3/4 8-2 8 3/4 3-1 B 3/4 3-1 B 3/4 3-la B 3/4 3-la

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TABLE 3.3-3 (Continued)

- ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRLMENTATION

.x "P

NINIMUM FUNCTIONAL UNIT kl5 R

ACTION m.

L4.

' MAIN STEAN LINE-c ISOLATION 5-Containment' Pressure -

4-2 --

3 1, 2, 3 2

a..

High'-

b.

Steam Generator Pressure - Low-

.4 2

3 1,2,3(c) 2:

5.-

ENCLOSt'RE BUILDING FILTRATION (EBFAS).

a.

Manualt EBFAS (Trip 2

1 2

1, 2, 3, 4 1

{

Buttons)-

i Y

b.

Manual'SIAS (Trip 2

1 2

1, 2, 3, 4 1-G Buttons)-

c.

Containment. Pressure-High 4

2.

3.

1, 2, 3 2-d.

Pressurizer Pressure -

Low 4.'

2 3

1,2,3(a) 2 t

6.

CONTAllMENT SUNP RECIRCULATION'(SRAS) 4

=

a.

Manual 1SRAS (Trip'

('

' Buttons);

2.-

1-.

2 1, 2,'3, 4 1:

.o.

b..

Refueling h ter.. Storage 5

Tank - La

~

_4 2..

3 1, 2, 3.

2!

.6 s

v

TABLE 3.3-4

.x "F

"G ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES 8

^

E ALLOWABLE bFUNCTIONALUNIT TRIP SETPOINT VALUES

_z l

• 1.

SAFETY INJECTION (SIAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable l

b.

Containment Pressure - High 4.75 psig 1 5.20 psig I

c.

Pressurizer Pressure - Low 2 1600 psia 2 1592.5 psia 2.

CONTAINNENT SPRAY (CSAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable y

b.

Containment Pressure -- High-High i 9.48 psig i 10.11 psig Y 3.

CONTAINMENT ISOLATION (CIAS) 5 a.

Manual CIAS (Trip Buttons)

Not Applicable Not Applicable b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable Containment Pressure - High 1 4.75 psig 1 5.20 psig c.

d.

Pressurizer Pressure - Low 2 1600 psia 2 1592.5 psia 4.

MAIN STEAM LINE ISOLATION Containment Pressure - High 1 4.75 psig 5 5.20 psig a.

b.

Steam Generator Pressure - Low 2 500 psia 2 492.5 psia g

a 8

e

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.... ~...

TABLE 3.3 5 fjillM ERED SAFETY FEATURES RESPONSE TIMES

~

It{lTIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECQtgli 1.

Manual a.

SIAS Safety injection (ECCS)

Not Applicable Containment isolation Not Applicable Enclosure Building Filtra'lon System Not Applicable b.

CSAS Containment Spray Not Applicable c.

CIAS Containment Isolation Not Applicable d.

SRAS Containment Sump Recirculation Not Applicable e.

EBFAS Enclosure Building Filtration System Not Applicable f.

Auxiliary Feedwater Initiation Not Applicable g.

Main Steam Isolation Not Applicable 2.

Pressurizer Pressure-Low a.

Safety Injection (ECCS) 1)

High Pressure Safety Injection 525.0*/5.0**

2)

Low Pressure Safety Injection s 45.0*/5.0**

3)

Charging Pumps 5 35.0*/35.0**

4)

Containment Air Recirculation s26.0*/15.0**

System-b.

Containment Isolation 5 7.5 c.

Enclosure Building Filtration System 145.0*/45.0**

~

Amendment No. 167 MILLSTONE - UNIT 2 3/4 3 21 cors-t

e TABLE 3.3-5 (Continued)

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

Containment Pressure - High a.

Safety injection (ECCS) 1)

High Pressure Safety injection s 25.0*/5.0**

2)

Low Pressure Safety injection 5 45.0*/5.0**

3)

Charging Pumps s 35.0*/35.0**

4)

Containment Air Recirculation System 1 26.0*/15.0**-

b.

Containment Isolation s 7.5 c.

Enclosure Building Filtration System s45.0*/45.0**

d.

Main Steam isolation s 6.9 e.

Feedwater Isolation 1 14 4.

Containment Pressure-Hich Hioh a.

Containment Spray 535.6*II)/16.0**II) 5.

Containment Radiation Hiah a.

Containment Purge Valves isolation s Counting period plus 7.5 6.

Steam Generator Pressure Low a.

Main Steam Isolation s 6.9 b.

Feedwater Isolation 5 14 7.

Refuelina Water Storaae Tank-low a.

Containment Sump Recirculation 1 120-8.

Steam Generator level-Low a.

Auxiliary feedwater System f 240*/240**(21 TABLE NOTATION Diesel generator starting and sequence loading delays included.-

Diesel generator starting and sequence loading delays att included.

Offsite power available.

1 Header fill time not included. -

2 Includes 3 n.inute time delay.

MILLSTONE - UNIT 2 3/4 3-22 Amendment No. 167

~

0078

TABLE 4.3-2 J

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRLHENTATION SURVEILLANCE REGUIREMENTS CHANNEL MODES IN WICH.

=, 3 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

~ r-

• 3 FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED S,

I. SAFETY INJECTION (SIAS) r

=

a.

Manual (Trip Buttons)

H.A.

N.A.

R N. A.

g b.

Containment Pressure - High S

R M

1, 2, 3 3

c.

Pressurizer Pressure - Low S

R M

1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

M(1) 1,i 2, 3 y

2. CONTAIMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

N.A.

N.A.

R N.A.

b.

Containment Pressure--

High - High 5

R M

1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

M(I) 1, 2, 3

3. CONTAIMENT ISOLATION (CIAS) a.

Manual CIAS (Trip Buttons)

N.A.

N.A.

R N.A.

N b.

Manual SIAS (Trip Buttons)

N.A.

N.A.

R N.A.

c.

Containment Pressure - High S

R M

1, 2, 3 Y

d.

Pressurizer Pressure - Low S

R M

1, 2, 3 0

e.

Automatic Actuation Logic N.A.

N.A.

M(1)

I, 2, 3

4. MAIN STEAM LINE ISOLATION a.

Containment Pressure--High S

R M

1, 2, 3 b

Steam Generator Pressure - Low S

R M

1, 2, 3 c

Automatic Actuation Logic N.A.

N.A.

M(1)

I, 2, 3 S. ENCLOSURE BUILDING FILTRATION (EBFAS) a.

Manual EBFAS (Trip Buttons)

N.A.

N.A.

R N.A.

)

y b.

Manual SIAS (Trip Buttons)

N.A.

N.A.

R N.A.

g c.

Containment Pressure - High S

R M

1, 2, 3 g-d.

Pressurizer Pressure - Low S

R M

1, 2, 3 g

e.

Automatic Actuation Logic N.A.

N.A.

M(1)

I, 2, 3 O.

I 4

ELECTRICAL POWER SYSTEMS ACTION (Continued) c.

With tw~o of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.2 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, unless the diesel generators are already operating restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

d.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in COLD SHUT 00WN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REOUIREMENTS 4.8.1.1.1 Two physically independent circuits between the offsite transmission network'and the switchyard shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying correct breaker alignments and indicated power availability.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the fuel oil supply tank, 2.

Verifying the diesel starts from ambient condition and accelerates to 2 90% of rated speed and to 2 977,of rated voltage in 1 15 seconds.

3.

Verifying the generator is synchronized, loaded to 11300 kw in 1 60 seconds, and operates for 1 60 minutes.

MILLSTONE - UNIT 2 3/4 8 2 Amendment'No. 167 0079

I i

f 3/4.3 INSTRUMENTATION gases 3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceedsitssetpoint,2)thespecifiedcoincidencelogicismaintained,

3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation,r accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time verification may be demonstrated by either 1).in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

The containment spray response time with a loss of normal m er assumes that the LNP occurs simultaneously with the CSAS. Therefore,=tte valve. stroke time is bounded-by the time required for signal generation, diesel start, sequencer, and time for the spray pumps to reach operating speed.

The containment spray response time without a loss of power is composed of signal generation and valve stroke time.

CAR fan response time is determined for the idle fan and conservatively applied to all four.

For the case with a loss of power, signal generation, diesel start, sequencer-and the time for the fans to reach operating speed bounds valvo stroke time.

MILLSTONE - UNIT 2 B 3/4 3 1 Amendment No. 167 0000

~

3/4.3.1 AND 3/4 2 2 PROTECTIVE AND ENGINEERED SAFETY FEATURES fESF) 2 INSTRUMENTA110N (Continued)

CAR fan response time for the case without a loss of power is composed of signal generation and valves stroke time.

Feedwater isolation response time ensures a rapid isolation of feed flow to the steam generators via the feedwater regulating valves, feedwater bypass valves and, as backup, feed pump discharge valvet. The response time includes signal generation time and valve stroke.

Feed line block valves also receive a feedwater isolation signal since the steam line break accident analysis credits them in prevention of feed line volume flashing in some cases.

Since the block valves are not credited with isolation, they are not required to operate as fast as the isolation valves although equal response times for all valves are specified.

The containment airborne radioactivity monitors (gaseous and particulate) are provided to initiate closure of the containment purge valves upon detection of high radioactivity levels in the containment.

Closure of these valves prevents excessive amounts of radioactivity from being released to the environs in the event of an accident.

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MILLSTONE - UNIT 2 B3/43-la Amendment No. 167 0000

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