Text

Amend 74 to License NPF-1,deleting Certain Tech Spec Requirements for Pump & Valve Testing Now Covered Under 10CFR50.55a
	ML20054F857
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/10/1982
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20054F856	List: ML20054F855; ML20054F857; ML20054F859;
References
	NUDOCS 8206180014
	Download: ML20054F857 (32)
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UNITED STATES NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D. C. 20555 t

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY

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DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-1 l.

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

A.

The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated April 28, 1982 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.1The facility will operate in confomity 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 -

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 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.

DESIGNATED ORIGIHAL Certified B

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/UI (jl c.-

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8206180014 820610 PDR ADOCK 05000344 P

PDR

e 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. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.

3.

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

FOR THk N,UCLEAR REGULATORY COMMISSION

/h.

if;j h Robert A. Clark, Chief l'

Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Spec fications Date of Issuance:

June 10, 1982 t

9, 1

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ATTACHMENT TO LICENSE AMENDMENT AMEND!!ENT NO.

TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 1-7 thru 3/4 1-14 3/4 1-7 thru 3/4 1-14 3/4 4-4 3/4 4-4 3/4 5-4 thru 3/4 5-6a 3/4 5-4 thru 3/4 5-6a 3/4 6-10 thru 3/4 6-13 3/4 6-10 thru 3/4 6-13 3/4 6-15 and 3/4 6-16 3/4 6-15 and 3/4 6-16 3/4 6-22 3/4 6-22 3/4 7-1 3/4 7-1

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3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 3/4-7-6a 3/4 7-11 3/4 7-11 3/4 7-13 thru 3/4 7-16 3/4 7-13 thru 3/4 7-16 B 3/4 4-1 B 3/4 4-1 e

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t REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN LIMITING CONDITION FOR OPERATION

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3.1.2.1 As a minimum, one of the following boron injection flow paths

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shall be OPERABLE:

a.

A flow path from the boric acid tanks via either a boric acid transfer pump or a gravity feed connection and charging pump to the Reactor Coolant System if only the boric acid storage tank in Specification 3.1.2.7a is OPERABLE, or b.

The flow' path from the refueling water storage tank via a charging pump to the Reactor Coolant System if only the refueling water storage tank in Specification 3.1.2.7b is. OPERAB_LE..

APPLICABILITY: MODES S and 6.

ACTION:

With none of the above flow paths OPERABLE, surpend all operations involving CORE ALTERATIONS or positive reactivity changes until at lea,.st one injection path is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demon-strated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the flow path is >65'F when a flow path from the boric acid tanks is used. -

b.

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

A TROJAN-UNIT 1 3/4 1-7 Amendment No. 7 4 l

4

i REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) c.

By verifying that each power operated or automatic valve in the flow path is OPERABLE when tested pursuant to Specification 4.0.5.

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.h TROJAN-UNIT 1 3/4'l-8 knendment No. 7 4

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 Each of 'the following boron injection flow paths shall be

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OPERABLE:

The flow path from the boric acid tanks via a boric acid a.

transfer pump and one charging pump to the Reactor Coolant System, and b.

The flow path from the refueling water storage tank via one charging pump to the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the flow path from the boric acid tanks inoperable, a.

-restore the-inoperable flow path 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 and' borated to a SHUTDOWN MARGIN equivalent to at least 1% ak/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 flow path 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 flow path from the refueling water storage tank inoperable, restore the flow path to OPERABLE status within 14 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 SHUTDOWN within the,following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:

At least once per 7 days by verifying that the temperature a.

of the flow path from the boric acid tanks is >65'F.

TROJ AN-UNIT 1 3 AI'1 9 -

Amendment No. 7 4 S

e REACTIVIT'i CONTROL SYSTEMS SURVEILLANCE PIOUIREMENTS (Continued) b.

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

By verifying that each power operated or automatic valve in c.

the flow path is OPERABLE when tested pursuant to Specifi-cation 4.0.5.

d.

At least once per 18 months, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a safety infection test signal.

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Amendment No. 7 4 TROJ AN-UNIT 1 3/4s1-10 m

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e REACTfVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.

)

SURVEILLANCE REOUIREMENTS 4.1.2.3 The above required charging pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge

, pressure >2400 psig when tested pursuant to Specification 4.0.5.

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3/4 1-1 TROJAN-UNIT 1 l

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Amendment No. 7 4 l

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1~, 2, 3, and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 at least two charging pumps 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 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge yressure of 12400 psig when tested pursuant to Specification 4.0.5.

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TROJAN-UNIT 1 3/4$-12 Amendment No. 7 4 O

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REACTIVITY CONTROL SYSTEMS BORIC ACID TRANSFER PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid transfer pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid transfer pump of Specification 3.1.2.la is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no boric acid transfer pump OPERABLE as required to complete the flow path of Specification 3.1.2.la, suspend all operations involving CORE ALTERATIONS 'or positive reactivity changes until at least one boric acid transfer pump is restored to OPERABLE status.

SURVEILLANCE REOUIREMENTS

,4.1.2.5 The above required boric acid transfer pump shall be demon-str,ated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of >105 psig when tested pursuant to Specification 4.0.5.

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i TROJAN-UNIT 1 3/4'l-13 '

Amendment No. 7 4 I

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REACTIVITY CONTROL SYSTEMS BORIC ACID TRANSFER PUMPS - OPERATING' LIMITING CONDITION FOR OPERATION 3.1.2.6 At least one boric acid transfer pump in the boric injection flow path required by Specification 3.1.2.2a shall be OPERABLE if the flow path through the boric acid transfer pump in Specification.3.1.2.2a

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is OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With no boric acid transfer pump OPERABLE, restore at least one boric acid transfer pump 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 borated to a SHUTDOWN MARGIN

, equivalent to at least 1% ak/k at 200*F; restore at least one boric acid transfer pump 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 .

e SURVEILLANCE REQUIREMENTS 431.2.6 The above required boric acid transfer pump shall be demon-strated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of >105 psig when tested pursuant to Specification 4.0.5.

J TROJ AN-UNIT 1 1

3/(71 Amendment No. 7 4 G

w e e w. ewe e me + ee-a m e w w

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a REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING SAFETY VALVES LIMITING CONDITION FOR OPERATION

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3.4.3.1 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG + 1%.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With a pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS - 4.4.3 No additional Surveillance Requirements othet,than those required by Specification 4.0.5.

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u. E l TROJ AN-UNIT 1 3/4'4-4 Amendment No. 56, 7,;

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that the following valves are in the indicated position with power to the operators removed:

Valve Number Yalve Function Yalve Position a.

MO 8806 a.

RWST Isolation a.

open*

b.

MO 8812 b.

RHR Suction b.

open*

c.

MO 8835 c.

SIS Cold Leg Injection c.

open*

d.

MO 8002-A d.

SIS Hot Leg Injection d.

closed e.

MO 8802-B e.

SIS Hot leg Injection e.

closed f.

M0'8703 f.

RHR Hog Leg Discharge f.

closed g.

MO 8809-A g.

RHR Cold Leg' Discharge g.

open*

h.

MO 8809-B h.

RHR Cold Leg Discharge h.

open*

1.

MO 8811-A 1.

Recir. Sump, RHR Suction 1.

closed

j. ' M01811-B - j. Recir. Sump, RHR Suction

j. closed

k.

MO 8813 k.

SI Pump Mini-flow isolation k.

open*

1.

MO 8814 1.

SI Pump Mini-flow isolation 1.

open*

b.

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

c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing containment integrity, and 2.

Of the areas affected within containment at the completion of each containment entry when containment integrity is established.

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Power to be restored and valves operated from within control room for switch from injection to recirculation mode following LOCA.

TROJAN-UNIT 1 3/P 5-4 Amendment No. 7 4 l

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months by:

1.

Verifying automatic isolation of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

3.

Verifying the correct position of each of the following ECCS manual throttle valves:

)

a)

Cold-Leg High-Pressure Boron Injection System Yalve, Numbers 8810A through D.

b)

Cold-Leg Safety Injection System Valve Numbers 8822A through D.

c)

Hot-Leg Safety Injection System g

Yalve Numbers 8816A through D.

e.

At least once per 18 months, during shutdown, by:

1 1.

Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

2..

Verifying that each of the following pumps start auto-matica11y upon receipt of a safety injection test signal:

a)

Centrifugal charging pump.

b)

Safetyinjectionpump.

c)

Residual heat removal pump.

3.

Yerifying that on a RWST--Low H nal the residual heat '

removal pumps are automatically de-energized.

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l TROJAN-UNIT 1 3/4'5-5 Amendment No. 24, 32, 7 4

I EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) f.

Following the completion of ECCS modifications that alter system flow characteristics by performing a flow balance test to verify the following injection flow rates:

1.

Cold-Leg High-Pressure Boron Injection System Each Injection Leg = 117 (+0, -5) gpm - Single Pump Operation 2.

Cold-Leg Safety Injection System Each Injection Leg = 158 (+5) gpm - Single Pump Operation 3.

Hot-Leg Safety Injection System Each Injection Leg = 325 (+0, -5) gpm - Applicable Pump Operation.with Train Isolation g.

Within four hours following completion of each valve stroking operation or maintenance on the valve when the subject ECCS is required to be OPERABLE by verifying the correct position of each of the following ECCS manual throttle valves:

' Sg 1.

Cold-Leg High-Pressure Boron Injection System Valve Numbers 8810A through D.

2.

Cold-Leg Safety Injection System Valve Numbers 8822A through D.

3.

Hot-Leg Safety Injection System Valve Numbers 8816A through D.

j h.

By verifying that each power operated or automatic valve t

in the flow path is OPERABLE when tested pursuant to i

Specification 4.0.5.

1.

By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

Amendment No. 7f, 32,7 4 3/(-5 6 l TROJ AN-UNIT 1 I

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o EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.

Centrifugal charging pump 12400 psig 2.

Safety injection pump 11455 psig 3.

Residual heat removal pump 1165 psig

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TROJAN-UNIT 1 3/4'5-6a Amendment No. 32, 7 4

m_

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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 4.6.2.1 Each containment spray system shall be demonstated OPERABLE:

a.

By verifying that on recirculation test line flow, each pump g'

develops a discharge pressure of >228 psig at a flow of >586 spm for FE-2066 and >227 psig at a flow of >592 gpm for TE-2067 when tested pursuant' to Specification 4.0.67 b.

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

At least once per 18' months, during shutdown, by:

c.

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray test signal.

2.

Verifying that each spray pump starts automatically.on a containment spray test signal.

3.

Verifying that on a RWST--Low-Low signal the spray pumps are automatically de-energized.

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TROJ AN-UNIT 1 3/4 6-10 ' '-

Amendment No. 7 i l

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CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) d.

At least once per 5 years by performing an air or smoke flow l

test through each spray header and verifying each spray nozzle is unobstructed.

e.

By verifying that each power operated (excluding automatic) valve in the flow path is OPERABLE when tested pursuant to Specification 4.0.5.

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2.

TROJ AN-UNIT 1 3/4 6-11 Amendment No. 7 4 A

l CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The spray additive system shall be OPERABLE with:

a.

A spray additive tank containing at least 3000 gallons of not

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less than 30 percent by weight NaOH solution, and b.

Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a containment spray system pump flow.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the spray additive system inoperable, restore the system to OPERABLE status within 72, hours 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 spray additive 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 REOUIREMENTS 4)6.2.2 The spray additive system shall be demonstrated OPERABLE:

a.

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

b.

At least once per 6 months by:

1.

Verifying the solution level in the tank, and 2.

Verifying the concentration.of the NaOH solution by chemical

analysis, c.

At least once per 18 months, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a containment spray test signal.

d.

At least once per 5 years by verifying a water flow rate of 37 + 3 gpm from the spray additive tank to each containment spray system with the spray pump operating in the recirculation mode through the test line..*

S.

TROJ AN-UNIT 1 3/d'6-12 Amendment No. 74

--,,,s,_

e a

CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) e.

By verifying that each power operated (excluding automatic) valve in the flow path is OPERABLE when tested pursuant to Specification 4.0.5.

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U TROJAN-UNIT 1 3/4 6-13 Amendment No. 7 4

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION YALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The cor.tainment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or d.

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 .

SURVEILLANCE REOUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demon-strated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demon-strated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Yerifying that on a containment isolation test signal, each isolation valve actuates +4 its isolation position.

i il TROJAN-UNIT 1 3/4 6-15 Amendment No. 7 4

1 i

CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) b.

Yerifying that on a Containment Ventilation isolation signal, each Purge valve and hydrogen vent valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

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TROJAN-UNIT 1 3/4 6-16 Amendment No. 23, 7 4 l

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T LE 3.6-1 CONTAINMENT ISOEATION VALVES U

TESTABLE DURING VALVE NUMBER FUNcIl0N PLANT OPERATION ISOLATION TIME b

(seconds)

S:

y D.

Containment Spray Actuation (Containment Isolation Barriers only)

M0 2053Af Containment Spray Pump A '

discharge - outside yes N.A.

MD 2053Bf Containment Spray Pump B '

discharge - outside yes N.A.

E.

Non-automatic Power Operated Valves i

MD 8702f((a)

RilR normal suction inside no N.A.

a)

MO 870lf RilR normal suction inside no N.A.

CV 8825#

RilR hot leg recirculation - inside no N.A.

m MO 8703#

RilR hot leg recirculation -

f'I outside no N.A.

3-MO 8835f SIS discharge line - outside P

(cold leg) no N.A.

MO 8809Al RilR pump "A" discharge - outside no N.A.

M0 8809Bf RilR pump "B" discharge - outside no N.A.

8

'MO 2069A SIS Recirculation Train "A" inside yes N.A.

M0 2052A SIS Recirculation Train "A" -

outside yes N.A.

pg MO 8811A SIS Recirculation Train A" -

a outside yes N.A.

g HD 20698 SIS Recirculation Train "B" g

sinside yes N.A.

M0 2052B SIS Recirculation Train "B" -

_.E outside yes N.A.

MO 8811B SIS Recirculation Train "B" 2

outside yes N.A.

(a) May be open during Mode 4 f

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3/4.7 ' PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

kPPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With 4 reactor coolant loops ind associated steam generators in

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operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron, Flux High Setpoint

' trip is reduced per Table 3.7-1; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

b.

With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

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either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-2; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

-c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings and orifice sizes as shown in Table 4.7-1, when tested pursuant to Specification 4.0.5.

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TROJAN-UNIT 1 3/4 7-1 Amendment No. 7 4-

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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

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1.

One feedwater pump capable of being powered by an OPERABLE

,esel with >450 gallons of fuel in its day tank, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

CTION:

. With.one auxiliary feedwater pump inoperable, restore the inoperable pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT' SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REOUIREMENTS 4).1.2.1 Each auxiliary feedwater pump shall be demonstated OPERABLE:

a.

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

I b.

By verifying that the diesel-driven pump starts and develops a discharge pressure of >1580 psig at 1200 RPM engine speed on recirculation ficw when tested pursuant to Specification 4.0.5.

c.

By verifying that the steam turbine-driven pump starts and develops a discharge pressure of >1580 psig at 4560 RPM on recirculation flow (when tested puFsuant to Specifi-cation 4.0.5) when the secondary steam pressure is

> 800 psig. Pump OPERABILITY may be determined at lower pressures in MODES 2 or 3 by verifying that the steam turbine-driven pump starts and develops a discharge pressure of > 1470 psig on recirculation flow (when tested A

s TROJAN-UNIT 1 3/4 7-5 Amendment No. 36, 7 4

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) pursuant to Specification 4.0.5) when the secondary steam pressure is > 275 psig; however, OPERABILITY at 4560 RPM shall be within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after secondary steam pressure is increased above 800 psig.

d.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

2.

Verifying that each pump. starts automatically upon l

receipt of each auxiliary feedwater actuation test signal in Table 4.3-2.

By verifying that eac'h power operated (excluding automatic) e.

. valve in the flow path is OPERABLE when tested pursuant to Specification 4.0.5.

4.7.1.2.2 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

'T 1.

Verify.ing the fuel level in its day tank, and 2.

Yerifying that a, sample of diesel fuel from its fuel tank is within the acceptable limits specified in Table 1 of ASTM D975-78 when checked for viscosity, water and sediment.

b.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to a inspection in accordance with procedures prepared in conjunction with its manufacturer's recomendations for this class of standby service, and 2.

Verifying the diesel and pump operate for _> 60 minutes.

I TROJ AN-UNIT 1 3/4 7-6 Amendment No. 39,-56,7 4

.s PLANT SYSTEMS MAIN STEAM LINE ISOLATION YALVES-LIMITING CONDITION FOR OPERATION 3.7.1.6 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES l', 2 and 3.

ACTION:

MODES 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; Otherwise, be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

MODES 2 - With one main steam line isolation valve inoperable, subsequent and 3 operation in MODES 1, 2 or 3 may proceed after:

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a.'

Th'e inoperable isolation valve is restored to OPERABLE status, or b.

The isolation valve is maintained closed; Otherwise, be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SU'RVEILLANCE RE0VIREMENTS r

4.7.1.6 Each main steam line isolation valve that is open shz11 be I

demonstrated OPERABLE by verifyino full closure within 5 secords when tested puriuant to Specification 4.0.5.

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TROJAN-UNIT 1 3/4'7-11 Amendment No. 7 4 4

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PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION

^

3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in COLD SHUTDOWN 1

within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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SURVEILLANCE RE0UIREMENTS 4

4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

.(manual, power operated or automatic)g that each valve At least once per 31 days by verifyin a.

servicing safety related equipment that is not locked, sealed, or otherwise

' '(

secured in position, is in its correct position.

b.

By verifying that each, Component. Cooling Water pump is OPERABLE when tested pursuant to Sepcification 4.0.5.

c.

At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety related equip-ment actuates to its correct position on a safety injection test signal.

i d.

By verifying that each power operated (excluding automatic) valve is OPERABLE when tested pursuant to Specification 4.0.5.

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TROJ AN-UNIT 1 3/4'7-13 '

Amendment No. 7 4 j

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l TROJAN-UNIT 1 3/4h-14 Amendment No. 74 8

a b

PLANT SYSTEM 3 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent service water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 .

)

SURVEILLANCE REOUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

,1 b.

By verifying that each service water and service water booster pump is OPERABLE when _ tested pursuant to Specification 4.0.5.

c.

At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety related equip-ment actuates to its correct position on a safety injection j

test signal.

i d.

By verifying that each power operated (excluding automatic) valve is OPERABLE when tested pursuant to Specification 4.0.5.

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TROJAN-UNIT 1 3/4'7-15' Amendment No.

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TROJ AN-UNIT 1 3/4N7-16 * -

Amendment No. 7 4 O

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o 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR CCCLANT LOOPS The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.73 during all normal operations and anticipated transients.

With one reactor coolant loop not in operation, THERMAL POWER is restricted to < 38 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset.

Either action ensures that the DNBR will be maintained above 1.73.

A loss of flow in two loops will cause a reactor trip if operating above P-7 (10 percent of RATED THERMAL POWER) while a loss of flow in one loop will cause a reactor trip if operating above P-8 (35 percent of RATED. THERMAL POWER).

A single reactor coolant loop provides' sufficient heat removal capability for removing core decay heat while in HOT STANDBY: however, single failure considerations require placing a RHR loop into operation

.in the shutdown cooling mode if component repairs andjor corrective

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actions cannot be made within the allowable out-of-service time.

3/4.4.2 SAFETY VALVES 3/4.4.3 SAFETY AND RELIEF VALVES The pressurizer code safety valves operate to prevent the RCS frem

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befog pressurized above its Safety Limit of 2735 psig.

Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at 110%

of the valve's setpoint.

The rel,ief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that-no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

Curing operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS frcm being pressurized above its safety limit of 2735 psig.

The combined relief capacity of all of these valves is ' greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip setpoint is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

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s TROJAN-UNIT 1 B 3/4 4-1 Amendment No. /B,EJ,7 4

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ML20054F857

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