Text

Amend 143 to License DPR-66,raising Max Allowed Svc Water Temp from 86 F to 90 F
	ML20247N632
Person / Time
Site:	Beaver Valley
Issue date:	07/27/1989
From:	Boger B; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20247N637	List: ML20247N632; ML20247N648;
References
	NUDOCS 8908030091
	Download: ML20247N632 (19)
	v • d • e

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UNITED STATES

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. NUCLEAR REGULATORY COMMISSION 4

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"DUQUESWE LIGHT COMPANY DHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 License No. DPR-56 1.

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

A.

The application for amendment by Duquesne Light Company, et al.

(the licensee) dated June 22, 1989 and supplement dated July 24, 1989, complies with the standards 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 confom15 with the application, the provisions of the Act, and the rt1r.; and regulations of the Commission; C.

There is reasonable assurance (1) t'nat the activities authorized by this ameadment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the hehlth 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.

AboCK P

L--_-__________

,s 2.

A:cordingly,rthe license is amended by changes to the Technical specifications as indicated-in the attachment to this license amendment, and paragraph 2.C.(?) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 143, are hereby incorporated in the license.

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

3.

This license amendmert is effective on issuance.

FOR THE NUCLEAR REGULATORY C0fe11SSION j

hl kl

- u s

Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

'Date of Issuance: July 27,1989 f

l J

L

ETACHMENTTOLICENSEAMENDMENTNO.143

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FAC1LITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following-pages of the Appendix A-(Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by (J

amendment number and contain vertical lines indicating the areas of change.

i\\

Remove insert 3/4 1-15 3/4 1-15 3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 3-22a 3/6 3-22a 3/4 3-27 3/4 3-27 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-5 3/4 6-5

'3/4 6-Sa 3/4 6-Sa 3/4 6-6 3/4 6-6 3/4 6-7 3/4 6-7 3/4 6-8 3/4 6-8 3/4 6-11 3/4 6-11 3/4 6-13 3/4 6-13 3/4 7-14 3/4 7-14 B3/4 6-2 B3/4 6-2

REAt;nvrrY wnrxOL SYSTEMS 1

BORATED WATER SOURCES - snuruGWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

{

A boric acid storage system with:

a.

1.

A ninimum *ontained volume of 5000 gallons, 2.

Between 7000 and 7700 ppm of boron, and 3.

A mininum solution temperature of 65*F.

b.

The refueling water storage tank with:

1.

A ninimum contained volume of 175,000 gallons, 2.

A minimum boron concentration of 2000 ppm, and 3.

A ninimum solution temperature of 45'F.

l AEELIcABILITY:

modes 5 and 6.

ACTION:

With no berated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one borated wuter source is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration of the water, 2.

Verifying the water level of the tank, and 3.

Verifying the boric acid storage tank solution temperature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water and i

the outside ambient air temperature is <45'F.

l BEAVER VALLEY - UNIT 1 3/4 1-15 Amendment No. 143 l

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~ 1EACTITITY CONTEtOL 'BYSTEMS BORATED WA M Euus h - OPF#1 TING LIMITING CONDITION'POR OPERATION

3.1.2.8 < As, a minimum,- the following borated veter source (s)

.shall be OPERABLE as required by specification 3.1.2.2.

a.

A. boric acid storage system with:

1.

A ninimum contained volume of 11,336 gallons, 2.

Between 7000 and 7700 ppa of boron, and 3.

A minimum solution temperature of 65'F.

b.

The refueling water. storage tank with:

1.

A contained volume between _ 439,050 gal 3pns and 441,100 gallons of borated water, 2.

A boron concentration between 2000 and 2100 ppa, and 3.

A solution temperature of 245'F and $55*F..

l APPLICABILITY:

MODES 1, 2, 3 & 4.

ACTION:

a.

With the beric acid storage system inoperable, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months be. in at least HOT STANDBY and borated to a SHUTDOWN or MARGIN equivalent to at least 14 delta k/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With

_the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour 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 SHU'tDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

BEAVER VALLEY - UNIT 1 3/4 1-16 Amendment tio.M.143

-___-_____-__.m__m__

4 REACTIVITY CONTROL NYSTEMS SURVEILLANCE REuumr.ru.n1S (Continued)

At least once per 7 days by:

a..

2.

Verifying.the boron concentration. in each water

source, 2.

Verifying the water-level in each-water source, and 3.

Verifying the boric acid storage system solution temperature.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the RWST' ambient air temperature is

<45'F or >55*F.

j j

i BEAVER VALLEY - UNIT 1 3/4 1-17 toend:nent No.143 l

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1 TABLE 3.3-5-(Continued)

ENGINyynyn nFETY FEaTtste awmPONSE r--a

, INITIATING SIGNAL AND FUNCTION RESPONSE TINE 15 BECONDS 4.

Stamm Line Pressure-Iow

a. -

Safety Injection -(ECCS)

S~27.04/37.06i b.

. Reactor Trip (from SI) s 3.0 c.

Feedwater Isolation S 75.0(1) d.-

-Containment Isolation-Phase."A" -

..S 22.0(3)/33.0 (2) e..

Auxiliary Feedwater Pumps Not Applicable f.

Rx Plant River Water System 5 77.O(3)/110.D (2)

I g.

Steam Line Isolation f

8.0-5.

Containment Pressure--Mich-Hich a._

Containment. Quench Spray 5 85.0(2) l' b.

Containment Isolation-Phase "B"

Not Applicable c.

Control Room Ventilation Isolation s 22.O(3)/77.0.(2) 6.

Steam Generator Water Level--Mich-Hioh a.

Turbine Trip-Reactor Trip 5

2.5 (Above P-9) b.

Feedwater Isolation 5 13.0(2) 7.-

Containment Pressure--Intermediate Mich-Hiah a.

Steam Line Isolation S

8.0 8.

Steamline Pressure Rate--Mich Necative a.

Steamline Isolation i

8.0 9.

Loss of Power a.

4.16kv Emergency Bus Undervoltage i

1.3 (Loss of Voltage) b.

4.16kv and 480v Emergency Bus s 95 Undervoltage (Degraded Voltage)

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i BEAVER VALLEY - UNIT 1 3/4 3-27 Amendment No.'4Q. M, M O, 1

M E, 143 I

Ge g t4en-letter-dated

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CDNTAIMMENT SYSTEMS CONTAINMENT 12&EAGE x

LIMITING CONDITION POR OPERATION

.3.6.1.2., Contm4*

leakage rates shall be limited to:.-

An overall integrated leakage rate of:

-m.

1

<_L',.

0.10 percent -by weight of.the. containment air p,er 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,' (40.0 psig), or l

.2.

A

. combined

leakage rate of s 0.60 L. for all

' penetrations and valves subject to -Type B,nd C tests a

as identified in Table 3.6-1, when pressurized to P.

a APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

l With either.

(a) the measured overall integrated containment leakage rate exceeding 0.75 L,

or (b) with the measured i

a combined leakage rate for all penetrations.and valves subject'to l

Types B

and C tests exceeding 0.60 L.,. restore the leakage rate (s)- to within the limit (s) prior to Increasing the Reactor coolant System temperature above 20D*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and -shall be determined in confornance with the criteria specified in Appendix J of 10 CFR 50* using the methods and provisions of ANSI N45.4-1972:

a.

A Type-A test (overall Integrated containment Leakage j

Rate) shall be conducted at 40 1 10-month intervals during shutdown at P. (40.0 psig).

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Exemption to Appendix J of 10 CFR 50, Section III.D.1(a),

granted on December 5, 1984.

,1 i

i Ii BEAVER VALLEY

UNIT'l 3/4 6-2 Amendment No. W. 143 1

m-p... ;

3-

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. CDNTAINIEENT. BYSTERES c

SURVETIZANCE REuv47.zru.wr5 (continued) b.

If any 1 periodic test schedule.:for ; subsequent. Type A test fails to meet.75 L.ll: be-

, the.

Type "A tests sha reviewed and approved by the Commission.

. If two-t consecutive Type A: tests fail to meet.75 L., a Type A test shall be performed at least every 18 months until. two consecutive Type. A tests meet

.75 L,at which time the above test schedule may be resumed.'

c.

The accuracy;of each Type A test shall'be verified by a supplemental test which:

1.

Confirms the. accuracy. -of the Type.A. test by verifying that the difference between supplemental and Type A test data.is within 0.25 L.

2.

Has a

duration sufficient to accurately establish' the change-in leakage for between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at 1, (4 0. 0 psig).

l j

d.

Type B and C tests shall Lee conducted with gas at P *(40.0 psig) at intervals no graatar than 24 monthe l

a 1

except for tests invoiving:

1 1

1.

Air locks,

.)

2.

Penetrations using continuous leakage monitoring systems, and 3.

Valves pressurized with fluid from a seal system, e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

j f.

Imakage from isolation valves that are sealed with fluid from a

seal system may be excluded, subject to the provisions of Appendix J,

section III.C.3, when determining the combined leakage sate provided the seal l

system and valves are pressurized to at least 1.10 P j

(44.0 psig) and the seal' system capacity is adequate to l

a 1

maintain system pressure for at least 30 days.

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)

Applicaole valves may be tested using water as the pressure l

fluid in accordance with the Inservice Testing Program.

BEAVER VALLEY - UNIT 1 3/4 6-3 Amendment No. T4,143

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I CCNTAINIENT BYST5MS i

CONTAINMENT AIR LDCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

i a.

Both. doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be I

closed, and 4

b.

An overall air lock leakage rate of less than or equal to 0.05 L at Pa (40.0 psig).

l J

a APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one containment air lock door inoperable:

a.

1.

Maintain the associated OPERABLE air lock door closed and either restore the associated inoperable air lock door to OPERABLE status Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the associated OPERABLE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leax. age test provided that the associated OPERABLE air lock door is verified to be locked closed at least once per 31 sfays.

3.

Otherwise, 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 .

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With a

containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock 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 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 .

BEAVER VALLEY - UNIT 1 3/4 6-5 Amendment No. T. M.143 Q

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/.

CONTATWMENT BYSTEMS 4l SURVEILLANCE REQUIREKu b j

_4.6.'1.3.J.ach, contai===t.

. air.

lock shall - be demonstrated OPERABIZ:

a.'

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each containment entry, except when the ' air lock is being used for multiple

entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying.

no detectable seal leakage when the gap between the door seals is pressurized for at least 2 minutes to:

1.

Personnel airlock 140.0 psig l

2.

Emergency air lock 2 10 0 Psig er, by quantifying the total air lock leakage to insure the requirements of 3.6.1.3.b are met.

b.

By conducting overall air lock leakage. tests, at not less than P (40.0 psig),

and verifying the overall l'

a air lock leakage rate is within its limit:

1.

At least once per 6 months, i and 2.

Upon completion of maintenance which has been performed on' the air lock that could affect the air loch sealing capability.*

c.

At least once per 18 months _during shutdown by verifying:

1.

Only one door in each air lock can be opened at a time, and 2.

No detectable seal leakage when the volume between the emergency air lock shaft seals is pressurized to greater than or equal to 40.0 psig for at.least l

2 minutes.

9 The provisions of Specification 4.0.2 are not applicable.

Exemption to Appendix J of 10 CFR 50, dated November 19, 1984.

BEAVEK VALLEY - UNIT 1 3/4 6-Sa Amendment No.$. %.143 L __-_ __-

+

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CONTAINMENT SYSTEMS INTERNAL PRESSURE I

LIMITING CONDITION FOR OPERATION l

3. 6.1. 4 Primary containment internal air partial pressure shall I

be maintained 2 B.9 PSIA and within the acceptable operation range (below.and-to the left of the applicable containment temperature limit line) shown on Flgure 3.6-1 as a lunction of river water temperature.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment internal air partial pressure < B.9 PSIA or above the applicable containment temperature limit line shown on l

Figure 3.6-1, restore the internal pressure to within the limits within 1

hour or be in at least HOT STANDBY within the next 6.

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

S_ SURVEILLANCE iu,vuuuuu.rrrS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

BEAVER VALLEY - UNIT 1 3/4 G-6 taendment No. 143

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NOTES:

10.6

1. MW5T TEMPERATURE BETWEEN 450F AND 558F.

10.5 2 MAXIMUM AL!DWAMLE CONTAINMENT --

TEMPERATURE 1050F, j

10.4

3. MINIMUM ALLOWABLE CONTNNMINT --

AIR PARTIAL PRESSURE.B.9 PSA, i

10.3-

4. MAxlMUM RNER WATER TEMERATURE 900F 10.2 CONTAINMEP T g-10.1

ig TEMPIAATul: E t 750F 0

o gg 10.0 3

E

\\

W 9.9 b~

W wh UN LCCEP"ASLE Ih OPERATION 3 a.

ACCEPTAB E O a 9.7 h$

OPE $tATIOP' Ii 9e N

9.5 2

9.4 9.3 C 3NTAthMENT rEMPE 4ATURI: 2950F %

MC 9.1 l

9.0 8.9 i

i 30 35 40 45 60

.66 60 66 70 75 80 86 l 90 88 RIVER WATER TEMPERATURE (OF)

FIGURE 3.61 MAXIM.UM ALLOWABLE PRIMARY CONTAINMENT AIR PRESSURE YERSUS RIVER WATER TEMPER ATURE BEAVER VALLEY - UNIT 1 3/4 6-7 Amendment No. $Z, 143

CONTAINMENT SYSTEMS AIR TEMPERATURE

. LIMITING CONDITION 70R OPERATION 3.6.1.5. Primary containment average air -temperature shall be maintained:

a.

. Greater than or equal to 75'F and less than nr. equal to 105'F, or b.

Greater than or equal to 95'F and less than or equal to 105'T in accordance with the requirements of Figure 3.6-1.

j APPLICA3ILITY:

MODES 1, 2, 3 and 4.

i ACTION:

With the containment average air temperature > 105'F or less than the minimum containment temperature prescribed in Figure 3.6-1 (75'T or 95'F) restore the average air. temperature to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least MOT STANDBY vithin 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 .

SURVEILLANCE REQUIREMENTS e

4. 6.1. 5 The primary containment average maximum and minimum air b

temperatures shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The nearest alternate thermocouple may be used for temperature determination up to a maximum of one per location.

Location a.

Reector Head Storage Area - Elev. 802

b.. Pressurizer Cubicle - Elev. 740 c.

Annulus - Elev. 777 d.

RHR Heat Exchanger - Elev. 730 e.

Annulus - Elev. 701 i

BEAVER VALLEY - UNIT 1 3/4 6-8 Amendment No. %,143 1

l a

CONTAIMEENT R BTEKS

\\

3 /4.4. 2 DErrr*SURI2ATION AND COOLTNG s1muns CONTAlnsEni OUEWCII SPRAY sVarrai Lin m wG CONDITION FOR OPERATION 3.6.2.1 Two separate and independent containment quench spray subsystems shall be OPIRABLE.

APPLICABILIII:

MODES 1, 2, 3 and 4.

ACTIOE:

With one containment quench spray subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 .

$URVP.ILIANCE RE7JIREMENTS 4.6.2.1 Each containment quench spray subsystem shall be demonstrated OPERABLET a.

At least once per 31 days by:

1.

Verifying that each valva (manual, power-operated, or automatic) in the flow path not locked, sealed, or otherwise secured in position, is in its correct position; and 2.

Verifying the temperature of the borated water in the refueling water storage tank is within the limits of Specification 3.1.2.8.b.3.

l b.

At least once per 31 days on a STAGGtRED TEST BASIS, by verifying, that on recirculation

flow, each pump develops a

differential pressure of great:r than or equal to 142 psid at a flow of 2, 1600 gpm when tested pursuant to specification 4.0.5, DEAVER VALLEY ~ UNIT 1 3/4 6-11 Amendment No. %, W,143 l

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~-

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CONTATMMENT ltEcimuutATION EPRAY Bimm LIMITING CONDITION FOR OPERATION 3.6.2.2 Four separate and independent containment-recirculation spray subsystems, each composed -of a spray pump, associated heat exchanger and flow path shall be OPERABLE.

APPLICABIIJTY:

MODES 1, 2, 3 and 4.

j.

ACTION:-

i I

containment recirculation spray subsystem inoperable,

'h With one restore the inoperable subsystem to CPERABLE status within 7 days. or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the

. inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment recirculation spray subsystem shall be demonstrated OPERABLE:

a.

At least-once per 31 days by verifying that each' accessible valve (manual, power-operated, or automatic) in the flow path not locked, sealed or otherwise secured in position, is in its correct position; b.

When tested pursuant to Specification 4.0.5, manually start each recirculation spray pump and verify the pump shaft rotates; c.-

At least once per 18 months by verifying that on a containment Pressure-High-High

signal, the recirculation spray

-pumps start automatically as follows:

RS-P-1A and RS-P-2B 210 1 5 second delay RS-P-2A and RS-P-1B 225 1 5 second delay d.

At least once per 18. months during shutdown, verify that on recirculation

flow, each pump develops the required differential pressure and flew rate as shown below when tested pursuant to specification 4.0.5:

RS-P-1A and.RS-P-1B 1 127 psid at 1 2000 gpm RS-P-2A and RS-P-2B 1 132 psid et 1 2000 gpa BEAVER VALLEY - UNIT 1 3/4 6-13 Amendment No. % 2, 143

_,_,,,_,,___,_n.a--

- - - - ~ ~ ~ - - "

C.

~{

2 l

PIANT WYSTE5tB h

3/4.7.5 tTLTIMATE WFAT EINK - OHIO RIVER LIMITING CONDITION FOR OPERATION 3.7.5.1 2he ultimate heat sink shall be OPERABLE with:

I I

a.

A minimum water level at or above elevation 654 Mean j

Esa Level, at the intake structure,-and b.

An average water temperature of 590'F.,

l, APPLICABILITY:

MODES 1, 2, 3 and 4.

AG219t[:

liith the requirernents-of the above specification not satisfied, 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 COLD SHUTDOWN withir. the follow:Ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RECJIREMENTS

=:em 4.7.5.1 The ultimate heat sink chall be determin64 OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water-tssperature and water level to be within their limits.

{

BEAVER VALLEY - UNIT 1 3/4 7-14

/cendment No. %, %t, 143

I s

4 1

CONTAT14 TENT EYSTEMS BASES I

3/4.6 1 4 and 3/4.6.1.5 ImamhL n -rsmustz AND ATR u.neme(ATURE limitations on containment internal pressure and average

.The air tampe::ature as a function of river water temperature ensure l

that 1) the containment structure is prevented froa exceeding

.its design negative pressure of s.0 psia, 2) the containment l

l peak pressura does no~

exceed the design pressure c1 45 psig during 10CA. conditions, and 3) the containment pres 50ee is returned to subatmospheric conditions following a LOCA.

I The containment internal pressure and temperature limits shown as a

function of river water temperature describe the l

operational envelope that will 1) limit the containment peak pressure to less than its design value of 45 psig and 2) ensure l

the cor.tainment internal pressure returns subatmospheric within 60 minutes following a LOCA.

The limits on the parameters of Figure 3.6-1 are consistent j

with the assumptions of the accident analyses.

3/4.6.1 6 CONTAINMENT STRUCTURAL INTEGRITY 2

This limitation ensures that the structural integrity of the containment vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 40.0 psig in the event of a LOCA.

The i

visual and Type A leakage tests are sufficient to demonstrate this capability.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.2 and 3/4.6.2.2 CONTAINMENT OUENCH AND RECIRCUJATIQE SPRAY SYSTEgg The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent return to subatmospheric pressure will occur in the event of a LOCA.

The pressure reduction and resultant termination of containment leakage are consistent with the assumptions used in the accident analyses.

3 BEAVER VALLEY - UNIT 1 B 3/4 6-2 6,nendment No

'.13

ML20247N632

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