Text

Proposed Tech Specs Re MSLB Design Limits
	ML20116C344
Person / Time
Site:	Millstone
Issue date:	10/28/1992
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20116C343	List: B14270, Application for Amend to License DPR-65,revising TSs as Result of Errors Discovered in MSLB Analysis; ML20116C344;
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	Download: ML20116C344 (9)
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4 Docket No. 50-245 B.1$219 1

Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Main Steam Line Break Design Limits Proposed Revised Pages October 1992 L

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TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION o 3:

F MINIMUM

G TOTAL NO.

HANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION M

4.

MAIN STEAM LINE c

ISOLATION 5

a.

Containment Pressure -

4 2

3 1, 2, 3 2

High b.

Stean._ Ge !cator i

Pressure Iow 4

2 3

1, 2, 3(c) 2 i

5.

ENCLOSURE BUILDING FILTRATION (EBFAS) i i

a.

Manual EBFAS (Trip 2

1 2

1, 2, 3, 4 1

g Buttons)

Y_

b.

Manual SIAS (Trip 2

1 2

1, 2, 3, 4 1

C Buttons) c.

. Containment Pressure-High 4

2 3

1,2,3 2

i d.

Pressurizer Pressure-Low 4

2 3

1,2,3(a) 2 f

6.

CONTAINMENT SUMP RECIRCULATION (SRAS) a.

Manual SRAS (Trip Buttons) 2 1

2 1, 2, 3, 4 1

b.

Refueling Water Storage Tank - Low 4-2 3

1,.2, 3 2

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ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION TRIP VALUES 9

m ALLOWABLE c: FUNCTIONAL UNIT TRIP SETPOINT VALUES 5-d'I.

SAFETr INJECTION'(SIAS) a.

Manual. (Trip Buttons)

Not Applicable Not Applicable b.

Containment. Pressure - High 4.75 psig s 5.20 psig c.

Pressurizer Pressure - Low 1 1600 psia 2 1592.F psia 2.-

CONTAINMENT SPRAY (CSAS) a.

Mantal (Trip Buttons)

Not Applicable Not Applicable

}{

b.

Containment Pressure -- High-High 1 9.48 psig i 10.11 psig T* 3.

CONTAINMENT ISOLATION (CIAS) 5; a.

Manual CIAS (Trip Buttons)

Not Applicable Not Applicable

~

b.

. Manual SIAS (Trip Buttons)

Not Applicable Not Applicable c.

Containment Pressure - High s 4.75 psig

$ 5.20 psig d.

Pressurizer Pressure - Low 1 1600 psia 1 1592.5 psia

[

t 4.

MAIN STEAM LINE ISOLATION

'[

a.

Containment Pressure - High 5 4.75 psig s 5.20 psig i

b.

Steam Generator Pressure - Low 1 500 psia 2 492.5 psta

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l IAB_LE 3.3 5 ENGINEERED SAFETY FEATURES RESPONSE TIMES I

INIllATING SIGNAL AUQ_fMiCll.QU ES_PONSE TIE _IN SECONQS 1.

damn].

a.

SIAS Safety injection (ECCS)

Not Applicable Containment 1selation Not Applicable Enclosure Building Tiltration System Not Applicable b.

CSAS Containment Spray Not Applicable c.

CIAS l

Containment Isolation Not Applicable d.

SRAS Lontainment Sump Recirculation Not Applicable e.

EBFAS

+

Enclosure Building filtration System hot Applicable f.

Auxiliary feedwater Initiation Not Applicable-g.

Main Steam Isolation Not Applicable 2..

Enquurizer Pressure La a.

Safety injection (ECC3) 1)

High Pressure S.ety injection s 25.0*/5.0**

2)

Low Pressure Safety injection _

s 45.0*/5.0**

3)

Charging Pumps s 30.0*/35.0**

4). ' Containment Air Recirculation 1 26.0*/15.0**

System l

l b.

Containment Isolation s 7.5 c.

Enclosure Building Filtration System-1 45.0*/45.0**

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f TABLE 3.3-5 Kontinued) 4 ENGINEERED SAFETY FEATURES RESPONSE TIMES JNITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

[pntainment Pressure - Hiah a.

Safety injection (ECCS) 1)

High Pressure Safety injection 1 25.0*/5.0**

2)

Low Pressure Safety injection s 45.0*/5.0**

3)

Charging Pumps 1 35.0*/35.0**

4)

Containment Air Recirculation System s 26.0*/15.0**

b.

Containment Isolation s 7.5 c.

Enclosure Building filtration System 1 45.0*/45.0**

d.

Main Steam Isolation s 6.9 e.

Feedwater Isolation 5 14 4.

Containment Pressure-Hich Hiah a.-

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

Certainment Radiation Hioh a.

Containment Purge Velves Isolation s Counting period plus 7.5 6.

11eam Geperator Pressure-Low s.

Main Steam isolation L 6.9 b.

Feedwater Isolation-

- 1.14 L

L 7.-

Rifuelina Water Storace Tankdgy a.

Containment Sump Recirculation s 120 8.

Steam Generator Level-Low-a.

Auxiliary Feedwater System.

1 235*/235**(2) lADLflLQIA11011

- Diesel generator' starting and sequence-loading delays included.

Diesel generator starting and sequence loading delays ng1 included.

Offsite power available.

(1) Header fill time not included.

(2)

Includes 3-minute time delay.

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TA9tE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

=x CHANNEL MODES IN WHICH.

U CHANNEL CHANNEL FUNCTIONAL

' SURVEILLANCE 3

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED o-5-

1. SAFETY INJECTION (SIAS) a.

Manual (Irip Buttons)

N.A.

R N. A.

g b.

Containment Pressure - High 5

R M

1, 2, 3 c.

. Pressurizer Pressure - Low S

R M

I,2,3 d.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 m

1

2. CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Containment Pressure--

1 High - High S

R M

1, 2, 3 c.

Automatic Actuation logic N.A.

N.A.

M(I) 1, 2, 3 l

3. CONTAINMENT ISOLATION (CIAS) a.

Manual CIAS (Trip Buttons)

N.A.

R N.A.

,)

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Containment Pressure - High 5

R M

1, 2, 3 4

d.

Pressurizer Pressure - Low S

R M

I,2,3 w

e.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3

4. MAIN STEAM LINE ISOLATION a.

Containment Pressure--High 5

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) 1, 2, 3

5. ENCLOSURE 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 - High S

R M

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

[LECTRICAL POWER SYSTEMS ACTION (Continued) c.

With two 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 oae bour and at least once per 8 hotc t thereafter, unless the diesel ganerators are already operating; restore at least one of the inoperable offsite-sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHVIDOWN within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With only one offsite source restored, restore-at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 .

Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE PEQUIREMENTS 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 tant,

2.

Ve ifying the diesel starts from ambient condition and accelerates to 2 90% of rated speed and to 2 97% of rated voltage in 1 15 seconas.

3.

Verifying the generator is synchronized, loaded to 2 1300 kw in s 60 seconds, and operates for 1 60 minutes.

MILLSTONE - UNIT 2 3/4 8-2 0079 1

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3/4.3 (NSTRUMENTATION BASES 3/4.3.1 AND 3/4.3.P---PR_0TECTIVE AND ENGlyfERED SAFETY FEATURES (EST)-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 initit.ted when the paranieter monitored by each channel or con.bination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained,

3) sufficient redundancy is maintained to permit a channel to le out of service for testing or maintenance, and 4) sufficient system functional capability is available for protectivt 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 of 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 aerformed at the minimum frequencies are sufficient to demonstrate this capa)ility.

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.

Respor.se 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 power assumes that the LNP occurs simultaneously with the CSAS.

Therefore, the valve stroke time is bounded bv the time required for signal generatien, 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 valve stroke time.

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3/11311 AND 3/4.3.2 PR0iECTIVE AND ENGINEERED SAFETY _EEATURES (ESF) l 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 valves. The response time includes e

signal generation time and valve stroke.

Feed line block valves also receive a feedwater isolation signal since the steam line break accident analysis i

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

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MILLSTONE - UNIT 2 B 3/4 3-la 0080

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ML20116C344

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