ML20141P020

Amends 72 & 46 to Licenses DPR-70 & DPR-75,respectively, Permitting Operation W/Only One Svc Water Header Operable During Modes 5 & 6 During Refueling Outage

ML20141P020
Person / Time
Site:	Salem
Issue date:	03/07/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141P021	List: ML20141P020 ML20141P024
References
NUDOCS 8603180437
Download: ML20141P020 (18)

Text

o* "G

1. c

%,'o, UNITED STATES l'

NUCLEAR REGULATORY COMMISSION e

E CASHWGTON. D C. 20555

• r *... + **

PURLIC SERVICE ELECTRIC AND GAS COMPANY PHILADFLPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATL ANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-27?

SALEM NUCLEAR GENEPATING STATION, UNIT NO. 1 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-70 1.

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

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated August 30, 1985 and supplemented by letter dated December 19, 1985, complies with the standards and requirements of the Atomic Eneroy 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph ?.C.(2) nf Facility Operating License No. DPR-70 is bareby amended to read as follows:

8603180437 860;K)/

PDR ADOCK 05000272 P

PDR

-2 (2) Technical Specifications The Technical Specifications contained in Appendices l

A and P, as revised through Amendment. No. 72. are t

hereby incorporated in the license. The licensee shall operste the facility in accordance with the Technical J

Specifications.

3.

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

F( b THE NUC AR GULATORY COMMISSION i

i

\\

do A

~

l even A.

argi, ctor PWR Project Direct r e #3 Division of PWR Lic ng-A

Attachment:

Changes to the Technical i

Specifications Date of Issuance:

March 7, 1986 i

1 i

L 2

J 4

4 4

l

.m

..---- m..

ATTACHMENT TO LICENSE AMENDMENT N0.72 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-?72 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 4-3b 3/4 4-3b 3/4 4-3c 3/4 9-Ba 3/4 9-8a B 3/4 4-1 B 3/4 4-1 B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 8 3/4 9-3

REACTOR COOLANT SYSTEM COLD SHUTD0bN B

LIMITING CONDITION FOR OPERATION 3.4.1.4 Twoe residual heat renoval loops shall be OPERABLE

• and at least one RHR loop shall be in operation.**

APPLICABILITY: MODE 5.##

ACTION:

a.

With less than the above required loops operable, inmediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b.

Mth no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and innediately initiate corrective action to return the required RHR loop to operation.

1 i

SURVEILLANCE REQUIREMENTS 4.4.1.4 At least one residual heat renoval loop snail be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

One RHR loop may be inoperable for up to two hours for surveillance a

testing, provided the other RHR loop is OPERABLE and in operation.

Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5% (narrow range).

A reactor coolant pump shall not be started with one or nare of the RCS cold leg temperatures less than or equal to 312*F unless 1) the i

pressurizer water volume is less than 1650 cubic feet (equivalent to approximately 92% of level), or 2) the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperatures.

Systems suptorting RHR loop operability may be excepted as follows:

a.

The norma? or emergency power source may be inoperable.

b.

One service water header Fay be out of service provided the equipment listed in Table 3.4-3 is OPERABLE.

The residual heat removal pumps rey be de-energized for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i

provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet i

temperature is maintained at least 10'F below saturation temperature.

SALEM - UNIT 1 3/4 4-3b Amendment No. 72 4

REACTOR COOLANT SYSTEM j

TABLE 3.4-3 MINIMUM EQJIPMENT REQUIRED FOR DECAY HEAT REMOVAL WITH ONE SERVICE WATER HEADER OUT OF SERVICE i

1 Both Residual Heat Removal Pumps, Heat Exchangers, and associated redundant flowpaths Two Component Cooling Pumps, one Component Cooling Heat Exchanger I

with operable flowpaths to each RHR Heat Exchanger j

Two Service Water Pumps l

Two Safety Grade Punps, in addition to the RHR pumps, capable 'of injecting makeup flow into the core (any conbination of safety j

injection ***, charging *** or containrent spray pumps) 1 i

1 One of the available pumps nay be administratively renoved fron i

service in order to conply with the requirenents of Section 3.5.3 i

footnote (8) and 4.5.3.2, provided that the pump can be nade j

operable within 15 minutes, i

r i

J t

l

}

t a

4 1

1 i

i l

I i

j SALEM - UNIT 1 3/4 4-3c Amendment No. 72 l

1 i

}

1 l

EFUEL!r4G OPEPAT!0'as LOW MTER LEVEL LIMIT!vi Cu'OIT

• M FOR OPEPATIO'i 3.9.3.2

, in in epandent Resitual 'at R? rov 11 (RER ) loops se 1'.

s

,P*.E.*

APPLIC A0ll!' t :

"0 E 6 ahen water level aMvc the t)p of the re:ty-

~

pressure vessel flange is less tnan 23 feat.

AC T !0'i:

i Luth less than the required RHR loops operable, innediately a.

i initiate corrective action to return the required RHR 1:o;s t).

Ori4A5LE status as soon as possible.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLA' ICE REl%IREMENTS i

4.9.8.2 The required Residual Heat Recoval loops shall te deterrins.1 OPEr(ABLE per Specification 4.0.5.

1 Systers supporting RH4 loop operability nay te excepted as '3113as:

The normal or energency power source may be inoperable.

a.

D.

One service water header nay be out nf service provided ;"e equi;rert listed in Table 3.4-3 is OPERABLE.

t l

l SALEM - V'4!T 1 3/4 9-Ba Amendment No. 72

l 3/4.4 REACTOR COOLANT SYSTEM j

BASES 3.

t 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION i

The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with less than all coolant loops j

in operation, this specification requires tnat the plant be in at least HOT i

STANOBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

j In MODE 3, a single reactor coolant loop provides sufficient heat remval for remving decay heat; but, single failure considerations require 6

all loops be in operation whenever the rod control system is energized and i

at least one loop be in operation when the rod control system is i

dee ner gi zed.

i i

in MODE 4, a single reactor coolant loop or RHR loop provides suf ficient heat remval for reroving decay heat; but, single failure considerations require that at least 2 loops be OPERABLE. Thus, if the i

reactor coolant loops are not OPERABLE, this specification requires that j

two RHR lonps be OPERABLE.

l In MODE 5, single failure considerations require that two RHR loops be 1

i OPERABLE. The provisions of Sections 3.4.1.4 and 3.9.8.2 [ paragraph (b) of j

footnote (*)] which permit one service water header to be out of service, j

are based on the following:

j

}

1.

The period of time during which plant operations rely upnn the f

provisions of this footnote shall be limited to a cumulative 45 days for 1

i any single outage, and l

2.

The Gas Turbine shall be operable, as a backup to the diesel l

generators, in the event of a loss of of fsite power, to supply the applicable loads. The basis for OPERABILITY is one successful startup of the Gas Turbine no rore than 14 days prior to the beginning of the Unit i

outage.

The operation of one Reactor Coolant Pump or one RHR Pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during Boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with Boron concentration reductions will, therefore, be within the capability of f

operator recognition and control.

i The restrictions on starting a Reactor Coolant Pump below P-7 with one or rore RCS cold legs less than or equal to 312'F are provided to prevent

)

RCS pressure transients, caused by energy additions from the secondary system, which cnuld exceed the limits of Appendix G to 10CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer (thereby providing a volume into which the primary coolant can expand, or (2) by restricting the starting of Reactor Coolant Pumps to those times when secondary water temperature in each st:am generator is j

less than 50*F above each of the RCS cold leg temperatures.

SALEM - UNIT 1 B 3/4 4-1 Amendment No. 72 l

1

+

REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE Tne OPERABILITY requirenents for the manipulator cranes ensure that:

1) nanipulator cranes will be used for novement of control rods and fuel assemblies, 2) each crane has suf ficient load capacity to lif t a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lif ting force in the event tney are inadvertently engaged during lif ting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on covenent of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 RES!UUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirenents that at least one residual heat remval loop be in operation ensures that (1) suf ficient cooling capacity is available t; remve decay heat and maintain the water in the reactor pressure vessel below 14U'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the ef fects of a baron dilution incident and prevent boron stratification. The requirenent to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat remval capability. The provisions of Sections 3.4.1.4 and 3.9.8.2 (paragraph (b) of footnote (*)] which permit one service water header to be out of service, are based on tne following:

1.

The period of tire during which plant operations rely upon the provisions of this footnote shall be linited to a cumulative 45 days for any single outage, and 2.

The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite power, to supply the applicable loads. The basis for OPERABILITY is one successful startup of the Gas Turbine no core than 14 days prior to the beginning of the Unit outage.

With the reactor vessel head remved and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate tine is provided to initiate energency procedures to cool the core.

I SALEM - UNIT 1 B 3/4 9-2 Amendment No. 72 I

?

1 j

f' REFUELING OPERATIONS i

i BASES I

3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATj i

f ine OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high The OPERABILITY of this systen e

radiation levels within the containrent.

j is required to restrict the release of radioactive material from the i

containment atmsphere to the environment.

L 1

3/4.9.10 and 3/4/9/11 WTER LEVEL - REACTOR VESSEL AND STORAGE P 1

i The restrictions on minimun water level ensure that sufficient water I

deptn is available to remve 99% of the assumed 10% iodine gap activity d

The minimun released from the rupture of an irradiated fuel assembly.

water depth is consistent with the assumptions of the accident analysis.

I 3/4.9.12 FUEL HANDLING AREA VENillATION SYSTEM The limitations on the fuel handling area ventilation systen ensure i

that all radioactive material released from an irradiated fuel assembly f

j will be filtered through the HEPA filters and charcoal adsorber prior to The OPERABILITY of this system and the l

j discharge to the atmsphere.

resultirg iodine remval capacity are consistent with the assumptions of l

i l

the accident analyses. ANSI N510-1975 should be used as a procedure j

j guideline for surveillance testing.

j i

i i

i i

i l

i i

i 1

f s

I i

}

i l

I l

i SALEM - UNIT 1 8 3/4 9-3 Amendment No. 72 l

1 t

I i

j t

_ _ = -

UNITED STATES o,,

8' NUCLEAR REGULATORY COMMISSION a

• b 8

CASHINGTON, D. C. 20666 s

%,.'..../

l PURLIC SERVICE ELECTDIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET I40. 50-311 SAL EM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.46 License No. DPR-75 1

f 1.

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

A.

The application for amendment by Public Service Electric and i

Gas Company, Philadelphia Electric Company, Delmarva Pnwer and Light Comp'any and Atlantic City Electric Company (the licensees) 4 dated August 30, 1985 and supplemented by letter dated Dacember 19, 1985, complies with the standards and requirements of l

the Atomic Energy Act of 1954, as amended (the Act) and the l

Commission's rules and regulations set forth in 10 CFR Chapter I; 1

l R.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission' 1

C.

There is reasonabla assurance (1) that the activities authorized by this amendment can be conducted without endangeriro the health a

and safety of *,he public, and (ii) that such activities will be

, conducted in ecmpliance with the Commission's regulationst D.

The issuance of this amendment will not be inimical to the ennmon j

defense and security or to the health and safety of the public; l

and i

4 E.

The issuance of this amendment is in accordance with 10 CFR Part I

51 of the Cortnission's regulations and all applicable requiremorts l

have been satisfied.

?.

Accordinolv, the license is amendad by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paraaraph ?.C.(2) of Facility Oparating License I

No. OPP-75 is hereby amendad to read es follows:

j c

4 f

I

l I.

-?-

l i

4, i

)

(2) Technical Specifications i

d l

The Technical Specifications contained in Appendices l

l

=

A and P as revised throuah Amendment No. 46, are

?

)

hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical i

i Specifications, j

1 1

3.

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

l F

THE NUC AR-R ULATORY COMMISSION i

)l

.i 1

t i

t /

dA I

{n

. V rgo, i

ctor j

i PWR Project Directo e #3 i

Division of PWR Lice ing-A i

i j

Attachment:

i Chancas to the Technical l

4 l

Specifications o

j Date of Issuance: March 7, 1986

[

I I

I 2

I I

I f

l 1

]

i i

i

[

i i

i r

i 1

I i

t l

1

1 ATTACHMENT TO LICENSE AMENDMENT NO.46 FACillTY OPERATING LICENSE NO. DPR-75 DOCKET NO.60-311 Revise Appendix A as fo110ws:

Pemove Paqas insert Pages 3/4 4-4a 3/4 4-4a 3/4 4-4b 3/4 9-9 3/4 9-9 8 3/4 4-1 8 3/4 4-1 9 3/4 9-?

B 3/4 9-2 8 3/4 9-3 8 3/4 9-3 l

l l

l

{

REACTOR COOLANT SYSTEM COLD SHUT 00

• LIMITING CONDITION FOR OPERATION 3.4.1.4 Two# residual heat reroval loops shall be OPERABLE

• and at least one RHR loop shall be in operation.**

APPLICABILITY: MODE 5.##

ACTION:

a.

Mth less than the above required loops operable, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b.

Mth no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operatinn.

SURVE!LLANCE RE0JIREMENTS 4.4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

One RHR loop may be inoperable for up to two hours for surveillance e

testing, pr.,vided the other RHR loop is OPERABLE and in operation.

Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to St (narrow range).

1. 1. A reactor coolant pure shall not be started with one or rore of the RCS cold leg temperatures less tnan or equal to 312*F unless 1) the pressurizer water volume is less than 1650 cubic feet (equivalent to approxinately 92% of level), or 2) the secondary water tenperature of each steam generator is less than 50*F above cach of the RCS cold leg temperatures.

Systems supporting RHR loop operability may be excepted as follows:

a.

The normal or emergency power source may be inoperable.

b.

One service water header may be out of service provided the equipment listed in Table 3.4-3 is OPERABLE.

The residual heat removal pumps may be de-energized for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation ter'perature.

SALEM - UNIT 2 3/4 4-4a Amendment No. 46

~.. _ _ _

t t

i REACTOR C00LANT SYSTEM t

i TABLE 3.4-3 MINIMON EQUIPMENT REQUIRE 0 FOR t

l OECAf HEAT REMOVAL WITH ONE l

SERVICE lATER HEADER DUT OF SERVICE I

f Both Residual Heat Removal Pumps, Heat Exchangers, and associated i

redundant flowpaths Two Component Cooling Pumps, one Component Cooling Heat Exchanger I

with operable flowpaths to each RHR Heat Exchanger Two Service Water Pumps 3

j Two Safety Grade Pumps, in addition to the RHR pumps, capable 'o f injecting makeup flow into the core (any combination of safety J

injection"*, charging *" or containment spray pumps) i j

One of the available punps may be adninistratively removed from t

i service in nerior to ennply with the requirements of Section 3.5.3 j

l footnote (s) and 4.').3.2, provided that the pump can be made operable within 15 minutes.

i

[

i f

i i

I i

i j

l i

I i

I

{

SALEM - UNIT 2 3/4 4-4b Amendrr.ent No. 46 l

l 1

4 i

l i

i i

l

\\

4 l

a REF UELING OPER AT!0'.S LOW 6%TER LEVEL LIMITING CONDITION FOR OPERATION 3.9.d.2 Tm inapandant R-sidual Fc3: Pro va t (RHR) 1,ys shal' :

, OPEd/ 3LE.*

APPLICa91LITY: MOCE 6 when water le.cl atowe tre tap of :ra rear. tar pressure vessel flange is less than 23 feet.

ACTION:

a.

With less than the required RHR loops operable, imredi3tel f initiate corrective action to return the required RHR loops to.

OPERABLE status as soon as possible, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RELU: REPENTS 4.9.8.2 The required Residual Heat Rernvil loops small be ceternined OPERABLE per Specification 4.0.5.

Systens supporting RHR loop operability naf be exceptsd as follons:

a.

The normal or erer9ency power saurce may be iroperable.

b '. One service water header ray be out of service proviced the equiprent listed in Tasle 3.4-3 is OPERABLE.

Amendment No. 46 SALEM - UNIT 2 3/4 9 ')

e l

3/4.4 REACVOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LO0pS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with less than all coolant loops in operation, this specification requires that the plant be in at least HOT STANDBY within I hour.

In MODE 3, a single reactor coolant loop provides suf ficient neat renoval I

for renoving decay heat; but, single failure considerations require all loops i

be in operation whenever the rod control system is energized ano at least one loop be in operation when the rod control systen is deenergized.

In MODE 4 a single reactor coolant loop or RHR loop provides suf ficient heat renoval for ren]ving decay heat; but, single failure consicerations require that at least 2 loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE. this specification requires that two RHR loops be O PER AB L E.

L In MODE 5. single f ailure considerations require that two RhR loops be OPERABLE. The provisions of Sections 3.4.1.4 and 3.9.8.2 (paragraph (o) of footnote (*)] which per mit one ser vite noter header to Ni nut of wrvice, are based on the following:

1.

The period of tine during which plant operations rely upon the provisions of this footnote shall be limited to a cunulative 45 days for any single outage, and 2.

The Gas Turbine shall be operable, as a backup b) the diesel generators, in the event of a loss of of f site power, to supply the i

applicaole loads. The basis for OPERABILITY is one successful startup of the Gas Turbine no more than 14 days prior to the beginning of the Unit outage.

The operation of one Reactor Coolant Punp or one RHR Panp provides adequate flow to ensure mixing, prevent stratification and produce gadcual reactivity cnanges during Boron concentration reductions in tre deactor Coolant Systen. The reactivity change rate associated with Baron concentration reductions will, therefore, be within the capaoility of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump below P-7 with one or mare RCS cold legs less than or equal to 312*F are provided to prevent RCS pressure transients, caused by energy additions from the secondary systen, which could exceed the limits of Appendix G to 10CFR Part 50. The RCS will be protected against overpressure transients and will not exceed tre limits of Appendix G by either (1) restricting the water volume in the pressurizee (thereby providing a volure into which the primary coolant can espard, or (2) by restricting the starting of Reactor Coolant Pumps to thos'e tines when secondary water temperature in each steam generator is less than dO'F above each of the RCS cold leg temperatures.

I SALEM - UNIT 2 8 3/4 4-1 Amendment No. 46

REFUELING 0PERA710NS BASES 3/4.9.6 MANIPULATOR CRANE l

l The OPERABILITY requirenents for the manipulator cranes ensure that:

1) manipulator cranes will be used for novenent of control rods and fuel assenblies, 2) each crane has suf ficient load capacity to lif t a control I

l rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lif ting force in the event they are inadvertently enpged during lif ting operations.

1 3/4.9.7 CRANE TAAVEL - SPENT FUEL STORAGE BUILDIN",

The restriction on novenent of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of l

fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assun.d in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION t

The requiremnts that at least ono residual heat remval loop be in operation ensures that (1) suf ficient cooling capacity is available to remve decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) suf ficient coolant circulation is maintained through the reactor core to minin12e j

the effects of a toron dilution incident and prevent boron stratification. The reovirenent to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat remval capability. The provisions of Sections 3.4.1.4 and 3.9.8.2 [paragrapn (b) of footnote (*)] which permit one service water header to be out of service, are based on the following:

1.

ine period of time during which plant operations rely upon the provisions of this footnote shall be limited tn a cumulative 45 days for anj single outage, and 2.

The Gas Turbine shall be operable, as a backup to the diesel l

generators, in the event of a loss of of fsite power, to supply the applicable loads. The basis for OPERABILITY is one successful startup of the Gas Turbine no mre than 14 days prior to the beginning of the Unit outage.

With the reactor vessel head remved and 23 feet of water above the re6ctor pressure vessel flange, a lary test sink is available for core cooling. inus, in the event of a failure of the operating RHR loop, adequate tire is provided to initiate energency procedure $ to cool the l

core.

l Amendment No. 46 l

SALEM - UNIT 2 8 3/4 9 2

HEF UELING OPER ATION,S BASES 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM, The OPERABILITY of this system ensures that the Containrent vent and purge penetrations will be automatically isolated upon detection of high rJdiation levels within the containrent. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environrent.

3/4.9.10 and 3/4/9/11 WATER LEVEL - REACTOR VESSf L AND STOR AGE POOL The restrictions on minimum water level ensure that suf ficient water depth is available to remove 99% of the assuned 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The mininum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM ine limitations on the fuel handling area ventilation system ensure that all radioactive material released frem an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to dischar ge to the atmosphere. The OPERABILITY of this system and the C.

resulting iodine reroval capacity are consistent with the assumptions of the accident analyses. ANSI N510-1975 should be used as a procedure guideline for surveillance testing.

SALEM - UNIT 2 0 3/4 9 3 Antndment No. 46

- -