ML20210D248

Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems

ML20210D248
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	07/20/1999
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20210D247	List: ML20210D243 ML20210D248
References
NUDOCS 9907270171
Download: ML20210D248 (19)

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_.

VERMONT Y ANKEE NUCLEAR POWER CORPORATION Docket No. 50-271 BVY 99-86

.d Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 219 High Pressure Core Cooling Systems Marked-up Version of the Current Technical Specifications

(

9907270171 990720 PDR ADOCK 05000271 P

PDR

r-i VYNPS 3.5 LIMITING CONDITION FOP 4.5 SURVEILLANCE REQUIREMENT l

OPERATION en the A.

,rnate 3.

From and af

1. Testing ng Tower System is that the found to be Cooling

a. A simulated automatic actuation 1*,

all active s f the Station made or test of the HPCI System shall ter System and inopera be performed during each ial equipment

reason,

% outage.

s shall have is pe be during

b. Operability testing of the pump to be seven Altern and valves shall be in accordance n 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

System with CWeation 4.6.E.

provid

c. Upon reactor startup, HPCI operability seven ll"yy{

testing shall be performed as P

required by Specification 4.6.E both a

\\ coolin within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding operab 150 psig reactor steam pressure.

4.

If the

d. The HPCI System shall deliver Specific at least 4250 gpm at normal cannot b*

reactor operating pressure shutdown a when recirculating to the

$1f1**ld*

Condensate Storage Tank.

1n shutdown condi 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

High Prsssure Cooling High Pressure Coolant Iniection (HPCI) System Injection (HPCI) System Surveillance of HPCI System shall be performed as follows:

fC f

1.

Except as snecified in Specificat.on 3.5.E.2, 1.

Testing whenever irradiated fuel is in the reactor vessel Item Frequ cy and reacto pressure is greate an 150 psi S

lated E

re-tomatic eling react y sta u o

r re cold p6ndi o N

ctuation outage N

Test g

a.

The HPCI System shall be operable.

Operabi ty testing of (N

the p' p and valves s 1

b.

The condensate be i accordance wi storage tank shall Sp ification 4.6 The I System sha deliver i

contain at least at least.4250 m at l

75,000 gallons of condensate water, normal react operating pressure w n recircul ing to the conden te Storage Tank. j Amendment No. 4p7., M4, 4M, 444, 169 105

1

~

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT

{

OPERATION 2.

From and after the date 2.

When the HPCI Subsystem that the HPCI Subsystem is made or found to be is made or found to be inoperable, the Automatic inoperable for any Depressurization System reason, reactor operation shall have been or shall is permissible only be demonstrated to be during the succeeding operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

seven days unless such subsystem is sooner made NOTE: Automatic operable, provided that Depre.surization during such seven days System operability all active components of shall be the Automatic demonstrated by Depressurization performing a Subsystems, the Core functional test of Spray Subsystems, the the trip system LPCI Subsystems, and the logic.

RCIC System are operable.

3.

If the requirements of #

Specification 3.5.E %

f, g-cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to $

sig within l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g, F.

Automatic Depressurization F.

Automatic Depressurization System System Surveillance of the Automatic Depressurization System shall be performed as follows:

1.

Operability testing of 1.

Except as specified in the relief valves shall

' Specification 3.5.F.2 below, the entire be in accordance with Automatic Specification 4.6.E.

Depressurization Relief System shall be operable at any time.the reactorM ressure is above psig and irradiated

-. -][/j[

fuel is in the reactor jgo vessel.

2.

From and after-the date 2.

Phen one relief valve of the Automatic Pressure

'd[le) that one of the four relief valves of the Relief Subsystem is made or found to be Automatic Depressurization inoperable, the HPCI Subsystem are made or Subsystem shall have been or shall be demonstrated found to be inoperable due to malfunction of the to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

electrical portion of the valve when the 106 Amendment No. 44, 444, 434, 164

MS

1. Testing

8. A simulated automatic actuation 3.5 LIMITING CONDITION FOR OPERATION test (testing Valve operabiftty) of the RCIC System sha!!be reactor is pressurized performed during each refueling abo psig with outage.

diated fuel in the reactor vessel, continued reactor operation is

b. Operability testing of the pump

/9 permissible only during and valves shall be in accordance the succeeding seven days With Specification 4.6.E.

unless such a valve is Upon reactor startup, RCIC operability soone; made operable, C.

provided that during such testing shall be performed as seven days both the required by Specification 4.6.E remaining Automatic Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> afterexceedin9 Rellaf System valves and 150 psig reactor steam pressure.

the HPCI System are operable.

d. The RCIC System sha!! deliver 3.

If the requirements of at least 400 gpm at nonnal i

Specification 3.5.F reactor operating pressure cannot be met, an orderly When recirculating to the shutdown shall be Condensate Storage Tank.

initiated and the reactor pressure shall be reduced l

to 5 sig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g.3 G.

Reactor Core Isolation G.

Reactor Core Isolation Cooling System (RCIC)

Cooling System (RCIC)

Surveillance of the RCIC System shall be performed as follows:

1.

Except as specified in 1

-= m nq Specification 3.5.G.2 below, the RCIC System Item Frequency shall be operable whenever the reacto Simula d Each re-pressure is than auto tic fueling 150 ps d irradiated act tion outage s in the reactor t t va

\\

2.

Fror and after the date operability)

NI]

that the RCIC System is made or found to be Operabilit testing of inoperable for any te pump nd valves shal reason, reactor operation ce in cordance with is permissible only Speci cation 4.6.E.

he during the succeeding RCI System shall d iver a

east 400 gpm 7 days unless such system is sooner made operable, rmal reactor erating provided that during such pressure when 7 days all active recirculatin to the Condensate torage Tank.

components of the HPCI A

System are operable.

Amendment No. M, M, 44, MG, 164 107

YYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION 3.

If the requirements of T Specification 3.5.G g

cannot be' met, an orderly M

Y. C G, /, c.

shutdown shall b.

initiated and the reactor pressure shall be reduced to 5 sig within l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g H.

Minimum Core and Containment H.

Minimum Core and Containment Cooling System Availability Cooling System Availability 1.

When one of the emergency l

1.

During any period when diesel generators is made l

one of the emergency or found to be diesel generators is inoperable, centinued inoperable, the remaining reactor operation is diesel generator shall have been or shall be permissible only during demonstrated to be the succeeding seven days, provided that all operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

of the LPCI, Core Spray and Containment Cooling Subsystems connecting to the operable diesel generator shall be operable.

If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Any combination of inoperable components in the Core and Containment Cooling Systems shall not defeat the capability of the remaining operable components to fulfill the core and containment cooling functions.

3.

When irradiated fuel is in the reactor vessel and the reactor is in the

old shutdown condition, all Core and Containment Cooling Subsystems may be inoperable provided no work is permitted which has the potential for j

draining the reactor vessel.

108 Amendment No. 33, 444, 164

lc VYNPS

'~

g:

3.5 (Cont'd)

SSW pump, SSW valve, etc.)

'- I taited to 15 days provided that durir

%wer supplies for t>'

' rt addition to componene The Automatic Depressurization System (ADS) consists of the alterne four safety-relief valves and serves as a backup to the High Pressure Coolant Injection System (HPCI). ADS is designed to If '

provide depressurization of the reactor coolant system during a j,

small t:reak loss-of-coolant accident if HPCI fails or is unable to maintain sufficient reactor waterlevel. Since HPCI operabirrty is h,

required above 150 psig, ADS operability is also required above E.

E this pressure.

fds ADS operation reduces the reactor pressure to within the operating pressure range of the low pressure coolant injection the and core spray systems, so that these systems can provide The EPC..

reactor Coolant inventory makeup.

' 'l,

the pipe t..

never uncove.

and clad temperaw

Reference:

Subsectic, F.

Automatic Depressurization Svstem The reli valves of the Act tic Depressurization ystem are a ha p

to the Is.

They enable e Core Spray Coolin ystem or I.FCI Sub tem to provide pro ction against the pipe break in e event o HPCI failure by de assurizing the react vessel rapidly ugh to ctuate the Core 5 ys or LPCI Subsyst Either of the t Core Spray Cooling Systems I.PCIs provides suff eat flow of coo e to prevent clad melting.

1 four relief valve are included in e Autematic Pressure Re of System.

(See

, FSAR.Yol. 4, ndix B.)

G.

Reactor Core Isolation Cooling System The Reactor Core Isolation Cooling System (RCIC) is provided to maintain the water inventory of the reactor vessel in the event of a main steam line isolation and complete loss of outside power without the use of the a

emergency core cooling systems. The RCIC meets this requirement.

Reference Section 14.5.4.4 FSAR. The BPCIS provides an incidental backup to the RCIC system such that in the event the RCIC should be inoperable no loss of function would occur if the RPCIS is operable.

E.

Mini ="- Core and Containment Cooline System Availability The core cooling and the containment cooling ~ subsystems provide a method j

of transferring the residual heat following a shutdown or ac:idsnt to a heat sink.

Based on analyses, this specification assures that adequate cooling capacity is available by precluding any combination of inoperable components from fulfilling the core and containment cooling function.

It is permissible, based upon the low heat load and other methods available to remove the residual heat, to disable all core and containment cooling l

systems for maintenance if the reactor is co'1d and shutdown and there is,

no potential for draining the reactor vessel. However, if refueling one diesel and operations are in progress, one coolant injection system, a residual of at least 300,000 gallons is required to assure core j

flooding capability.

j lila Amendment No. 37., M4, 169

VYNPS M

4.5 G2e AND CoWTADeGW Coon amM A.

Core serav and C.Per During mesmal plant operation, manual tests of operable pumps and valves shall be conducted in accordance with Specification 4.6.E to desmastrate operabi,11ty.

• During each refueling =h*h, tests (as summarized below) aball be conducted to demonstrate proper automatic operation and system performance.

d11 demonstratar

[

e-

"tions HPCI system testing demonstrates operational readiness of equipment and detects degradations which may afect reliable operation. Testing is conducted during each reactor startup if maintenance that affects operability was performed on the HPCI system. Periodic testing is also performed in accordance with Specification 4.6.E and the inservice testing program.

Sufficient steam flow must be available prior to HPCI testing to avoid inducing an operational transient when steam is diverted to the HPCI system. Reactor startup is allowed prior to performing the required I

I surveillance testing in order to achieve adequate steam pressure and flow.

However, a 24-hour limitation is imposed for performing operability testing once reactor steam pressure exceeds 150 psig. The short duration before full functional testing is performed is considered acceptable.

-. ~t ~

o...

conPaf ama-D.,

E., and F.

station S< Mee water and Alternate Cooline Tower Systems j

I and Mich T. scw Coolant Iniection and Automatic Decressuri.zation system l

3e iag deser in Speci tion 4.6.E theIPCISystemwi1Q trate that system 1 operate i _ _ ired A Autamasas wtages to avoid pepressurzzatton system as sessoa auring an undesirable blowdown of the Beactor Coolant System.

the EPCI Automatic Actuation Test will be performed by simulation of the accident signal. The test is normally perfor: sed in conjunction with the automatic actuation of all core standby cooling Systems.

l C.

Reactor Core Isolation Cooline system of te ng of the

• c system i same as EPCI, per fFr s

icacion

.6.E.

and a=trates the syst s operable if

1. ed.

d The frequency and cced;t;cis for testing of the RCIC r,

system are the same as for the HPCI system. Testing is

~1!

conducted in accd.r.ce with n +?- +%n 4.6.E and r

provides assurance that the system will function as 113 Ameno-intended.

._ d*

VYNPS 4.6 SURVIII.IANCE REQUIREMENTS LIMITING CONDITIONS FOR 3.6 GriiATION Safety and Relief Valves D,

Safety =ad Relief Valves D.

Operability testing of 1.

During reactor power Safety and Relief Valves i

1.

operating conditions and shall be in accordance whenever the reactor

• with Specification coolant pres 4.6.E.

The lift point is greater than sig of the safety and relief and temperature valves shall be set as ter than 350*F, both specified in valves and at least Specification 2.2.B.

three of the four relief valves shall be p

operable.

If Specification 3.6.D.1 2.

is not met, initiate orderly shutdown I

e reactor coolant shall be below psig and 350*F wi 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

structural Intecrity and E.

structural Intearity and

_Ocerability Testina E.

coerability Testinc Inservice inspection of 1.

The structural integrity and safety-related the operability of the components shall be safety-related systems and performed in accordance components shall be with Section II of the maintained at the level ASME Boiler and Pressure required by the original vessel Code and acceptance standards applicable Addenda as throughout the life of the required by 10 CFR 50, plant.

Section 50.55a(g),

except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

Inservice inspectiun of piping, identified in p

NRC Generic Letter 88-01, shall be performed in accordadce with the staff positions on schedule, methods, and personnel and sample expansion included in the Generic Letter.

l 120 Amendment No. N, M, M, M, Me, 4M,160 i

VERMONT YANKEE NUCLEAR POWER CORPORATION 1

Docket No. 50-271 BVY 99-86 i

l Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 219 liigh Pressure Core Cooling Systems Retyped Technical Specification Pages 4

l i

VERMONT YANKEE NUCLEAR POWER CORPORATION BVY 99-86 / Attachment 4 / Pige I Listine of Affected Technical Specifications Panes Replace the Vermont Yankee Nuclear Power Station Technical Specifications pages listed below with the revised pages. The revised pages contain vertical lines in the margin indicating the areas of change.

Remove Insert 105 105 l

106 106 107 107

~108 108 lila lila 112*

112*

113 113 114 114 120 120 Due to the addition of text on page 111a, text overflow affects page 112. The content of page 112 is otherwise unchanged.

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION 3.

From and after the date 3.

When the Alternate that the Alternate Cooling Tower System is Cooling Tower System is made or found to be made or found to be inoperable, all active inoperable for any components of the Station reason, reactor operation Service Water System and is permissible only toth essential equipment

]

during the succeeding cooling loops shall have seven days, unless the been or shall be Alternate Cooling Tower demonstrated to be System is made operable, operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

provided that during such seven days all active components of the Station j

Service Water System and q

both essential equipment cooling loops are operable.

4.

If the requirements of Specification 3.5.D

{

cannot be met, an orderly j

shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

High Pressure Cooling E.

High Pressure Coolant Injection (HPCI) System In$ection (HPCI) System Surveillance of HPCI System shall be performed as follows:

1.

Except as specified in

1. Testing Specification 3.5.E.2, whenever irradiated fuel

a. A simulated automatic i

is in the reactor vessel actuation test of the and reactor steam HPCI System shall be pressure is greater than performed during each 150 psig:

refueling outage.

a.

The HPCI System

b. Operability testing of shall be operable, the pump and valves shall be in accordance b.

The condensate with Specification storage tank shall 4.6.E.

contain at least 75,000 gallons of

c. Upon reactor startup, condensate water.

HPCI operability testing shall be performed as required by Specification 4.6.E within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 150 psig reactor steam pressure.

Amendment No. M, 444, 448, -144, 449 105

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION 2.

From and after the date

d. The HPCI System shall that the HPCI Subsystem deliver at least 4250 is made or found to be gpm at normal reactor inoperable for any operating pressure when reason, reactor operation recirculating to the is permissible only Condensate Storage during the succeeding Tank.

seven days unless such subsystem is sooner made 2.

When the HPCI Subsystem operable, provided that is made or found to be during such seven days inoperable, the Automatic all active components of Depressurization System the Automatic shall have been or shall Depressurization be demonstrated to be Subsystems, the Core operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Spray Subsystems, the LPCI Subsystems, and the NOTE: Automatic RCIC System are operable.

Depressurization System operability 3.

If the requirements of shall be either Specification demonstrated by 3.5.E or Specification performing a 4.5.E.1.c cannot be met, functional test of an orderly shutdown shall the trip system be initiated and the logic.

reactor pressure shall be reduced to s 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

F.

Automatic Depressurization F.

Automatic Depressurization System System Surveillance of the Automatic Depressurization System shall be performed as follows:

1.

Except as specified in 1.

Operability testing of Specification 3.5.F.2 below, the entire the relief valves shall Automatic be in accordance with Depressurization Relief Specification 4.6.E.

System shall be operable at any time the reactor steam pressure is above 150 psig and irradiated fuel is in the reactor vessel.

2.

When one relief valve of 2.

From and after the date the Automatic Pressure that one of the four relief valves of the Relief Subsystem is made or found to be Automatic Depressurization inoperable, the HPCI Subsystem are made or Subsystem shall have been or shall be demonstrated found to be inoperable due to malfunction of the to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

electrical portion of the valve when the Amendment No. M, 444, MB, M4 106

r l

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT j

OPERATION 1

reactor is pressurized l

above 150 psig with irradiated fuel in the reactor vessel, continued reactor operation is permissible'only during the succeeding seven days unless such a valve is sooner made operable, provided that during such seven days both the remaining Automatic j

Relief System valves and the HPCI System are l

operable.

3.

If the requirements of Specification 3.5.F cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to s 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

G.

Reactor Core Isolation G.

Reactor Core Isolation Coolini System (RCIC)

Cooling System (RCIC) 1 Surveillance of the RCIC System shall be performed as follows:

1.

Except as specified in

1. Testing Specification 3.5.G.2 below, the RCIC System

a. A simulated automatic shall be operable actuation test (testing whenever the reactor valve operability) of steam pressure is greater the RCIC System shall than 150 psig and be performed during irradiated fuel is in the each refueling outage.

reactor vessel.

b. Operability testing of 2.

From and after the date the pump and valves that the RCIC System is shall be in accordance made or found to be with Specification inoperable for any 4.6.E.

reason, reactor operation is permissible only

c. Upon reactor startup, during the succeeding RCIC operability 7 days unless such system testing shall be is sooner made operable, performed as required provided that during such by Specification 4.6.E 7 days all active within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after components of the HPCI exceeding 150 psig System are operable.

reactor steam pressure.

Amendment No. 44, 34, 444, 434, 164 107 t

l l

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION 3.

If the requirements of

d. The RCIC System shall either Specification deliver at least 400 3.5.G or Specification gpm at normal reactor 4.5.G.l.c cannot be met, operating pressure when an orderly shutdown shall recirculating to the be initiated and the Condensate Storage reactor pressure shall be Tank.

l reduced to s 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

H.

Minimum Core and Containment H.

Minimum Core and Containment Cooling System Availability Cooling System Availability 1.

During any period when 1.

When one of the emergency one of the emergency diesel generators is made diesel generators is or found to be inoperable, continued inoperable, the remaining reactor operation is diesel generator shall j

permissible only during have been or shall be the succeeding seven demonstrated to be days, provided that all operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j

of the LPCI, Core Spray and Containment Cooling Subsystems connecting to the operable diesel generato* shall be operab!s.

If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Any combination of inoperable components in the Core and Containment Cooling Systems shall not defeat the capability of the remaining operable components to fulfill the core and containment cooling functions.

3.

When irradiated fuel is in the reactor vessel and the reactor is in the cold shutdown condition, all Core and Containment Cooling Subsystems may be inoperable provided no work is permitted which has the potential for draining the reactor vessel.

Amendment No. M, 444, 444 108

VYNPS BASES:

3.5 (Cont'd)

SSW pump, SSW valve, etc.), then reactor operation is limited to 15 days provided that during this time both the normal and emergency power supplies for the remaining operable equipment are also operable, in addition to demonstrating the operability of all remaining active components of the SSW system which perform a safety function and the alternate cooling tower fan.

If the SSW System would not be capable of performing its safety function for any reason, even without assuming a worst case single active failure, then the reactor must be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

High Pressure Coolant Injection System The High Pressure Coolant Injection System (HPCIs) is provided to adequately cool the core for all pipe breaks smaller than those for which the LPCI or Core Spray Cooling Subsystems can protect the core.

The HPCIs meets this requirement without the use of outside power.

For the pipe breaks for which the HPCIs is intended to function the core never uncovers and is continuously cooled; thus, no clad damage occurs and clad temperatures remain near normal throughout the transient.

Reference:

Subsection 6.5.2.2 of the FSAR.

F.

Automatic Depressurization System The Automatic Depressurization System (ADS) consists of the four safety-relief valves and serves as a backup to the High Pressure Coolant Injection System (HPCI). ADS is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident if HPCI fails or is unable to maintain sufficient reactor water level.

Since HPCI operability is required above 150 psig, ADS operability is also required above this pressure.

ADS operation reduces the reactor pressure to within the operating pressure range of the low pressure coolant injection and core spray systems, so that these systems can provide reactor coolant inventory makeup.

G.

Reactor Core Isolation Cooling System The Reactor Core Isolation Cooling System (RCIC) is provided to maintain the water inventory of the reactor vessel in the event of a main steam line isolation and complete loss of outside power without the use of the emergency core cooling systems.

The RCIC meets this requirement.

Reference Section 14.5.4.4 FSAR.

The HPCIS provides an incidental backup to the RCIC system such that in the event the RCIC should be inoperable no loss of function would occur if the HPCIS is operable.

H.

Minimum Core and Containment Cooling System Availab'ility The core cooling and the containment cooling subsystems provide a method of transferring the residual heat following a shutdown or accident to a heat sink.

Based on analyses, this specification assures that adequate cooling capacity is available by precluding any combination of inoperable components from fulfilling the core and containment cooling function.

It is permissible, based upon the low heat load and other methods available to remove the residual heat, to disable all core and containment cooling systems for maintenance if the reactor is cold and shutdown and there is Amendment No. M, 444, 449 111a

VYNPS BASES:

3.5 (Cont'd)

.no potential for draining the reactor vessel.

However, if refueling operations are in progress, one coolant injection system, one diesel and a residual of at least 300,000 gallons is required to assure core flooding capability.

I.

Maintenance of Filled Discharge Pipe Full discharge lines are required when the core spray subsystems, HPCI and RCIC are required to be operable to preclude the possibility of damage to the discharge piping due to water hammer action upon a pump start.

Amendment No. 18 112

VYNPS BASES:

4.5 CORE AND CONTAINMENT COOLANT SYSTEMS A.

Core Spray and LPCI During normal plant operation, manual tests of operable pumps and valves shall be conducted in accordance with Specification 4.6.E to demonstrate operability.

During each refueling shutdown, tests (as summarized below) shall be conducted to demonstrate proper automatic operation and system performance.

Periodic testing as described in Specification 4.6.E will demonstrate that all components which do not operate during normal conditions will operate properly if required.

The automatic actuation test will be performed by simulation of high drywell pressure or low-low water level.

The starting of the pump and actuation of valves will be checked.

The normal power supply will be used during the test.

Testing of the sequencing of the pumps when the diesel generator is the source of power will be checked during the testing of the diesel.

Following the automatic actuation test, the flow rate will be checked by recirculation to the suppression chamber.

The pump and valve operability checks will be performed by manually starting the pump or activating the valve.

For the pumps, the pump motors will be run long enough for them to reach operating temperatures.

B. and C.

Containment Spray Cooling Capability and RHR Service Water Systems The periodic testing requirements specified in Specifications 4.5.B and l

C will demonstrate that all components will operate properly if required. Since this is a manually actuated system, no automatic j

actuation test is required.

The system will be activated manually and the flow checked by an indicator in the control room.

Once every five years air tests will be performed to assure that the containment spray header nozzles are operable.

D.,

E.,

and F.

Station Service Water and Alternate Cooling Tower Systems and High Pressure Coolant Injection and Automatic Depressurization System HPCI system testing demonstrates operational readiness of equipment and detects degradations which may affect reliable operation.

Testing is conducted during each reactor startup if maintenance that affects operability was performed on the HPCI system.

Periodic testing is also performed in accordance with Specification 4.6.E and the inservice testing program.

Sufficient steam flow must be available prior to HPCI testing to avoid inducing an operational transient when steam is diverted to the HPCI system.

Reactor startup is allowed prior to performing the required surveillance testing in order to achieve adequate steam pressure and flow.

However, a 24-hour limitation is imposed for performing operability testing once reactor steam pressure exceeds 150 psig.

The short duration before full functional testing is performed is considered acceptable.

Amendment No. 34, 444, 444, 113

VYNPS BASES:

1.5 (Cont'd)

]

The Automatic Depressurization System is tested during refueling outages to avoid an undesirable blowdown of the Reactor Coolant System.

The HPCI Automatic Actuation Test will be p'.riormed by simulation of the accident signal.

The test is normally p formed in conjunction with the automatic actuation of all Core Standby Cooling Systems.

G.

Reactor Core Isolation Cooling System The frequency and conditions for testing of the RCIC system are the same as for the HPCI system. Testing is conducted in accordance with Specification 4.6.E and provides assuranca that the system will function as intended.

H.

Minimum Core and Containment Cooling System Availability Assurance that the diesels will perform their intended function is obtained by the periodic surveillance test and the results obtained frc' the pump and valve testing performed in accordance with ASME Section XI requirementa described in Specification 4.6.E.

Whenever a diesel is inoperable, the potential for extended operation with two diesels inoperable is reduced by requiring that the redundant diesel be tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I.

Maintenance of Filled Discharge Pipe Observation of water flowing from the discharge line high point vent as discussed in Section I assures that the Core Cooling Subsystems will not experience water hammer damage when any of the pumps are started.

1 I

Core Spray Subsystems and LPCI Subsystems will also be vented through the discharge line high point vent following a return from an inoperable status to assure that the system is " solid" and ready for operation.

i Amendment No. 44, 34, 444, 444, 114

VYNPS 3.6 LIMITING CONDITIONS FOR 4.6 SURVEILLANCE REQUIREMENTS OPERATION D.

Safety and Relief Valves D.

Safety and Relief Valves 1.

During reactor power 1.

Operability testing of operating conditions and Safety and Relief Valves whenever the reactor shall be in accordance coolant pressure is with Specification 4.6.E.

l greater than 150 psig and The lift point of the temperature greater than safety and relief volves 350*F, both safety valves shall be set as specified and at least three of the in Specification 2.2.B.

four relief valves shall be operable.

2.

If Specification 3.6.D.1 it not met, initiate an orderly shutdown and the reactor coolant pressure l

shall be below 150 psig and 350*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

Structural Integrity and Operability Testing E.

Structural Integrity and Operability Testing The structural integrity and the operability of the 1.

Inservice inspection of safety-related systems and safety-related components components shall be shall be performed in maintained at the level accordance with required by the original Section XI of the ASME acceptance standards Boiler and Pressure throughout the life of the Vessel Code and

plant, applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a (g) (6) (i).

Inservice inspection of piping, identified in NRC Generic Letter 88-01, shall be performed in accordance with the staff positions on schedule, methods, and personnel and sample expansion included in the Generic Letter.

Amendment No. M, M, 44, M, Me, M9,MO 120

l 123 Main Street White Plains. New York 10601 914 681.6950 914 2873309 (Fox)

A NewYorklbwer s - xaes.i 4# Authority Bre75[5*e$$$*e"r* *"d July 16,1999 IPN-99-078 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 1

Subject:

Indian Point 3 Nuclear Power Plarit Docket No. 50-286 License No. DPR-64 Supplement to Proposed Changes to Technical Specifications 1.10,3.6 & 4.4 fhgprdina the Removal of the Containment isolation Valve Tables

]

Reference:

NYP/ letter to NRC (IPN-99-010), " Proposed Changes to Technical Specifications 1,10,3.6 & 4.4 Regarding the Removal of the Containment Isolation Valve Tables,"

dated January 28,1999.

Dear Sir,

The referenced letter submitted a proposed license amendment to sections 1.10,3.6 and 4.4 of the Indian Point Unit 3 (IP3) Technical Specifications (TS). That submittal proposed removing Containment isolation Valve (CIV) Tables 3.6-1 and 4.4-1 and making related changes to TS 1.10, 3.6.A and 4.4, as well as the associated TS bases. This supplement modifies TS 3.6.A.1 and the TS bases section of TS 3.6, " Containment System" to include additional information concerning administrative controls for those non-automatic CIVs, including locked or sealed closed valves, to be opened intermittently for plant operation. This is in response to an NRC request. This supplemental chan; to the TS and TS bases closely models the Standard Technical Specifications (STS), NUREG-1C..

Attachment I contains the prcposed new TS and bases pages 3.6-1,3.6-3 and 3.6-3a. The only change to an actual specification is to TS 3.6.A.1. This does not change the interit of what was previously submitted. It adds the requirements of administrative controls that already exist in TS 1.10.1, to better link these two specifications together. These attached TS pages,3.6-1 and 3.6-3, should be used in lieu of those submitted in the referenced letter. Page 3.6.3a is added for repagination in support of this change. All other TS pages submitted with the referenced letter should be used as submitted. Attachment 11 is a revised version of the safety evaluation, submitted with the referenced letter, with revision bars indicating changes that describe the revised TS pages.

Please note that there is no change to the associated "no significant hazards" evaluation. 11, a markup of the proposed ITS section 3.6.3 bases pages to reflect these changes, is submitted for information only.

\\

['

ll 9907270184 990716 PDR ADOCK 05000286 P

PDR

1 Docket No. 50-286

~

IPN-99-078 Page 2 of 2 e

In accordance with 10CFR50.91, a copy of this supplement is being submitted to the designated New York State official.

As previously noted, this Technical Specification change impacts valve testing during the upcoming refueling outage at Indian Point 3. Therefore, it is requested that this license amendment be dispositioned prior to the start of the outage, scheduled for September 10,1999.

If you have any questions, please contact Mr. Ken Peters, IP3 Licensing Manager, at (914) 736-8029.

Very truly yours J.Knubel Senior Vice President and Chief Nuclear Officer Attachments cc:

Mr. Hubert J. Miller, Regional Administrator, Region l U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 l

Resident inspector's Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Weshington Avenue Extension Albany, NY 12203-6399 Mr. George F. Wunder, Project Manager Project Directorate i Division of Reactor Projects 1/II U.S. Nuclear Regulatory Commission Mail Stop 8 C4 Washington, DC 20555 J