Text

Amends 83 & 55 to Licenses DPR-70 & DPR-75,respectively, Revising Tech Specs Re Boron Concentration in Refueling Water Storage Tanks & Accumulators
	ML20236B211
Person / Time
Site:	Salem
Issue date:	10/16/1987
From:	Bulter W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20236B214	List: ML20236B211; ML20236B216;
References
	NUDOCS 8710260013
	Download: ML20236B211 (24)
	v • d • e

2 1'

]

.s

'f[pa asoq

'o UNITED STATES g

NUCLEAR REGULATORY COMMISSION

(

g l

E WASHINGTON, D. C. 20$55 i

i g

0 4

4 9

PLIBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY i

ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 1

SALEM NUCLEAR G'ENERATING STATION, UNIT NO. 1

~

AMENDMENT TO FACILITY OPERATING LICENSE i

1 Amendment No 83 l

License No. M -70

-]

1.

The Nuclear Regulatory Commission (the Comission or the NRC)> has found that:

A.

The application for amendment filed by the Public Service Elc.ctric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated i

March 10, 1987, and supplemented by letters dated June 24, 1987 and July 9, 1987, complies with the standards and requirements of.the 1

l Atomic Energy Act of 1954, as amended (the'Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the l

provisions of the Act, and the rules and regulations of the Comission; 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be. inimical to. he comon t

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

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of l

the Commission's regulations and all' applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as. indicated in the attachment to this license amendmant, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 4s hereby I

amended to read as follows:

1 I

8710260013 87.101'6 PDR ADOCK 05000272 P

PDR 1

....s_

i s

q 2-(2) Technical' Specifications and ~ Environmental Protection Plan The' Technical Specifications contained lin Appendices A and.B, as-revised through Amendment'No. 83

. are hereby incorporated in the

. license.

The licensee shall operate the facility in accordance with the Technical Specifications, l

3.

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

[

l FOR THE: NUCLEAR REGULATORY COMMISSION j

/s/,

a

' Walter R. Butler, Director.

~

- Project Directorate I-2 Division of Reactor Projects I/II

.j

Attachment:

Changes to the Technical

' Specifications Date of Issuance: October 16, 1987 l

i J

q PDI PD

[

GC PDI-2/D M

DFischer 66 WButler -

L /87 7h,f/87

~ jo/e/87.

(O / /87.-

\\

a

2..

(?). Technical Specifications' and Environmental Protection Plan

'The' Technical Specifications contained.in Appendices-A an'd_B. as1 revised through Amendment'No. 83 ', are-herebylincorporated in:the; license. =The licensee shall operate the facility in accordance with' the Technical Specifications,.

3.

This license anendment> is effective as of its date of issuance,

l..

FOR THE. NUCLEAR REGULATORY COMMISSION 1 l

/j f r A

Walter R. Butler Director.

j Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications q

Date of Issuance: October 16, 1987-l

~

G, i

'---__.-_______--____._.-_-_m_

l ATTACHMENT TO LICENSE AMENDMENT NO. 83 1

FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Pevise Appendix A as follows:

Remove Pages Insert Pages 3/4 1-1 3/4 1-1.

3/4 1-3 3/4 1-3 3/4 1-14 3/4 1-14 3/4 1-16 3/4 1-16 3/4 5-1 3/4 5-1 3/4 5-7 3/4 5-7 3/4 10-1 3/4 10-1 l

B 3/4 1-3 8 3/4 1-3 i

B 3/4 5-2 B 3/4 5-2 f

._m___

____._._____w

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORAT10N CONTROL SHUTDOWN MARGIN Tavg > 200*F LIMITING CON 0! TION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be 1-1.6% ak/k.

APPLICABILITY: MODES 1, 2*, 3, and 4 ACTION:

With the SHUTDOWN MARGIN < i.6% ok/k, immediately initiate and continue boration at > 10 gpm of 20,000 ppm boric acid solution or equivalent l-until the required SHUT 00WN' MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall. be determined to be 1 1.6% ak/k:

Within one hour af ter detection of an inoperable control. rod (s) a.

and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable. If the inoperable control rod is innovable or untrippable, the above required SHUTOOWN MARGIN shall be i

increased by an amount at least equal to the withdrawn worth of the imovable or untrippable control rod (s).

b.

When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal.is within the limits of Specification 3.1.3.5.

When in M00d 2", within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor c.

criticality by verifying that the predicted critical control rod position is.within the limits of specification 3.1.3.5.

See Special Test En ception 3.10.1

W1th K 1 1.0 HWith K,ff eff < 1.0 SALEM - UNIT 1 3/4 I-I Amendment No. 83

c REACTIVITY CONTROL SYSTEMS SHUTOOWN MARGIN - T,yg <,200*F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTOOWN MARGIN shall.be 3,1.0% ak/k.

APPLICABILITY: MODE 5..,

1 ACTION:

With the SHUTDOWN MARGIN < 1.0% ak/k, immediately initiate and continue boration at 2,10 gpm of 20400 ppm boric acid solution or l

equivalent until the required SHUT 00WM MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTOOWN MARGIN shall be determined to be > 1.0% ak/k:

Within one hour after detection of an inoperable control. rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is a.

inoperable. If the' inoperable control' rod is immovable or untrip-pable, the SHUTOOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s).

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following b.

factors:

1.

Reactor coolant syste'm boron concentration, 2.

Control rod position, 3.

Reactor coolant system average temperature, Fuel burnup based on gross thermal energy generation, 4.

5.

Xenon concentration..and 6.

Samarium concentration.

SALEM - UNIT 1 3/413 Amen &nant No. 83

\\

l 1

a REACTIVITY CONTROL SYSTEMS 80 RATED WATER SOURCES - SHUTDOWN a

1 t

LIMITING CONDITION FOR OPERATION 4

3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

'i a.

A boric acid storage system and at. least one associated heat tracing system with,i j

1.

A minimum contained volume of 835 gallons, 1

I 2.

Between 20,000 ano 22,500 ppm of boron, and, l

q

)

3.

A minimum solution temperature of.145'F.

b.

The refueling water storage tank with:

j 1.

A minimum contained volume of 12,500 gallons, l

t 2.

A minimum boron concentration of.2300 ppm, ana l

3.

A minimum solution temperature of 35'F.

l APPLICABILITY: MODES 5 and 6.

l

]

ACTION:

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

i SURVEILLANCE REQUIREMENTS j

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

a.

At least once per 7 days by:

1 1.

Verifying the boron concentration of the water, s

j 2.

Verifying the water level of the tank, and j

3.

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

~

SALEM - UNIT 1 3/4 1-14 Amendment No. 83 i

i l

1

V

-REACT IVITY CONTROL SYSTEMS -

BORATE D WATER SOURCES - OPERATING l

LIMIT!NG CONDITION FOR OPERATION _

3.1.2.8 Each ofsthe' following borated water sources shall be OPERARLE:

a.

A boric acid storage system and at least one associated heat tracing-r system with:

1.

A minimum contained volume of 5106 gallons, 2.

Between 20,000'and 22,500 ppm of boron, and, I.

3.

A minimum solution temperature of 145'F.

b.

The refueling water storage tank' with:

1.

A contained volume of between 364,500'and 400,000 gallons of water, l

1 2.

A boron concentration of between 2,300 and 2,500 ppm, and-l-

3.

A minimum solution temperature' of 35'F.

l l

APP LIC AB I LITY: MODES 1, 2, 3 and 4 l

ACT10N:

I l

I a.

With the boric acid storage system inopraele and being used as one of the above ~ required boration water systems, restore.the storage system to OPERABLE status wihin 72-hours 'or be-in at least HOT. STANmY within l

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHWDOWN MARGIN equivalent to at-l l

1 east 1% delta K/k at.200*F; restore the boric acid storage system to OPERABLE status within the next ~7 days or be in COLD SHWOOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the refueling water storage tank inoperable,-restore the tank to OPERABLE status within one hour or be in at least HOT STANCBY within l

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 .

i SURVEILLANCE REQUIREMENTS 3

1' l

4.1. 2. 8 Each borated water source shall be demonstrated OPERABLE:

L SALEM - UNIT 1 3/4 1-16 Amendment No. 83 i.

L_____.__--___._-______

a

-g.

j t,

. )

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ACCUMULATORS 4

LIMIT!NG CONDITION FOR OPERATION 3.5.1 Each reactor coolant system accumulator shall be OPERABLE Eith:

a.

The isolation valve open, b.

A contained volume' of between 6,223 and - 6,500 gallons.of l

borated' water,'

.i c.

A baron concentration of between 2,200 and.12,500 ppm,l-

-1

and, I

i d.

A nitrogen cover-pressure of between 595.5 and 647.5 psig.

APPLICABILITY: -MODES 1, 2 and 3.*

e ACTION:

.l a..

With one accumulator _ inoperable, except as a result of a closed-isolation valve, restore the inoperable accumulator to OPERABLE:

status within one hour or be in HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With one accumulator. inoperable due to the. isolation valve being-closed,'either immediately open the isolation valve or:be. in HOT -

1 STAND 8Y within"one. hour and be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1 Each accumulator shall be demonstrated OPERABLE:

1 a.

At feast once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying the water level and nitrogen cover-pressure in the tanks, and 2.

Verifying that each acc'umulator isolation. valve 15' open.

' Pressurizer Pressure above 1000 psig.

mannchant sno. 83 '

SALEM - UNIT 1 3/4 5 1 P

/

.m

.__.._mu_____m

O g.

i EMERGENCY CORE COOLING SYSTEMS

- REFUE LING' WATER STORAGE TANK LIMITING CONDITION FOR~ 0PERATION 3.5.4 The refueling water storage tank (RWST).shall'be OPERAB LE with:

a.

A contained volume of between 364,000 and 400,000 of borated w' ate'r.

l

i b.

A boron concentration of between 2,30'0 and-2,500 ppm, and l

c.

A minimum water temperature of 35'F.

APP LICAB I LITY: HOES 1, 2, 3 and 4 ACTION:

4 With the. refueling water storage tank inoperable, restore the tank to OPERAB LE.

status within' 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be.in at least HOT STANGY within 6. hours and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the water level in the tank', and 2.

Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is < 35*F. -

t I

i SALEM - UNIT 1 3/4 5 7 Amendment No. 83

3/4.10 SPECIAL TEST EXCEPTIONS

-l SHUT DOWN MARGIN LIMITING CONDITION FOR OPERATION-

i. _

3.10.1 The SHUT DOWN MARGIN requirement of Specification 3.1.1.1 ma'y be suspended'for measurement of control rod worth and shutdown margin provided the-l reactivity ' equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERAB LE control rod (s), and i

1 APP LIC AB I LITY: MO CE 2.

1 i

i ACT ION:

With any full length control rod not fully inserted and with less than the.

a.

abov6' reaeti vity equi yalent auallable fcr trip imertim, 4==H*1y irdtie ard l

l continue boration at > 10 gpm of 20,000 ppm boric acid solution or its l

equivalent until the THUTDOWN MARGIN require'd by Specification 3.1.1.1.is restored.

1 b.

With all full length control. rods inserted and the reactor subtritical by less than the above reactivity equivalent, immediately initiate and continue boration at > 10 gpm of 20,000 ppm boric acid Solution or its l

equivalent until the THUT DOWN MARGIN ' required by Specification. 3.1.1.1 is restored.

l SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length and part length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

l 4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable l

of full insertion when tripped from at least the.50% withdrawn position within l

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of l

Specification 3.1.1.1.

l SALEM - UNIT 1 3/4 10-1 Amendment No. 83

I 1

REACTIVITY CONTROL SYSTEMS u

i BASES i

4 3/4.1.2 BORAT10N SYSTEMS The boron injection system ensures th'at negative reactivity control is

. i available during each mode of f acility operation. The components required to j

perform this function include:

1) borated water sources,.2) charging pumps, 3) 1 separate flow paths, 4) boric acid transfer pumps, 5) associated heat tracing systems, and 6) an emergency power supply from OPERAB LE diesel. generators.

With the RCS average temperature

above 200*F,.a minimum of two boron injection flow paths are required to ensure single functional capability in the f

event an assumed f ailure renders one of the flow paths inoperable. The boration j

capability of either flow path is sufficient to. provide a SHUT 00WN' MARGIN f rom-expected ' operating conditions of 1.6% delta k/k af ter xenon decay and cooldown to 200*F. The maximum expected boration capability requirement occurs at EOL from full power equilibrum xenon conditions and requires 5106 gallons of 20,000 ppm borated water from the boric acid storage tanks or 85000 gallons of 2300 ppm borated water f rom the refueling water storage tank. However, to be consistent with the ECCS requirements, the RWST is required to have a minimum contained volume of 350,000 gallons during operations 'in MODES 1,' 2, 3 and 4. -

With the RCS temperature below 200'F, one injection system is acceptable.

without single f ailure consideration on the basis of the' stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the' event the single-injection system becomes inoperable.

The boron capability required below 200'F is sufficient to provide a SHUTDOWN MARGIN of it delta k/k after xenon decay and cooldown from 200'F to 140*F. This condition requires either 835 gallons of 20,000 ppm borated water i

from the boric acid storage tanks or 12500 gallons of 2300 ppm borated water from the refueling water storage tank.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

SALEM

. UNIT 1 B 3/4 1-3 Amendment No. 83

-.---__m_______m_m

EMERGENCY CORE COOLING SYSTEMS BASES l

3/4.5.4 REFUELING VATER STORAGE TANK l

l The OPERABILITY of the RVST as part of the ECCS ensures that a sufficient supply of borated water.is available for injection by i

the ECCS in the event of a LOCA.

j l

The limits on RWST minimum volume and boron concentration ensure that:

(1) sufficient water is available within containment to permit-recirculation cooling flow to the core, (2) the reactor will remain l

l suberitical in the cold condition following a small LOCA assuming-l complete mixing of the RWST, RCS, and ECCS water volumes with Ell l

control rods inserted except the'nost reactive control assembly (ARI-1), and (3) the reactor will resin suberitical in the cold l

condition following a large break LOCA (break flow area > 3.0 sq. ft.)

assuming complete mixing of the RWST, RCS, and ECCS water and other sources of water that may eventually reside in the sump following a l

LOCA with all control rods assumed to be out (ARO).

The limits on contained water volume and boron concentration also

)

ensure a pH value of between 8.5 and 11.0 for the solution i

recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the offeet of chloride and caustic stress corrosion on mechanical systems and f

components. The contained water volume limit includes an allevance l

for water not usable because of tank discharge line location or other physical characteristics.

)

i s

i l

4 l

l l

b SALEM - UNIT 1 8 3/4 5-2 Amen & ment No. 83

)

I l

~,

pa ar%,Io, UNITED ST ATES

[',ei fi NUCLEAR REGULATORY COMMISSION W ASHING TON D. C. 20555 g

l s,; *~ f

'l

...+

PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA' POWER AND LIGHT COMPANY ATLANTIC' CITY ELECTRIC. COMPANY DOCKET NO. 50-311_

J l

SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 i

4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-75 The Nuclear Regulatory Comission (the Comission or the NRC) has found 1.

that:

J The application for amendment filed by the Public Service Electric &

A.

Gas Company, Philadelphia Electric Company,(Delmarva Power and Company and Atlantic City Electric Company the licensees) dated March 10, 1987 and supplemented by letters dated June 24, 1987, and l

July 9,1987, complies with the standards and requirements of the L'

AtomicEnergyActof1954,asamended.(theAct),andthe Comission'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 Comission; There is reasonable assurance: (ilthattheactivitiesauthorizedby j

C.

this amendment can be conducted without endangering the health and j

safety of the public, and (ii) that such activities will be conducted l

in compliance with the Comission's regulations set forth in 10 CFR l

Chapter I; i

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 l

I The issuance of this amendment is in accordance with 10-CFR Part 51 of e

l E.

i the Comission's regulations and all applicable requirements have been

)

satisfied.

Accordingly, the license is amended by changes to the Technical Specifica-2.

tions as indicated in the attachment to this license amendment, and

.i i

paragraph 2.C.(?) of Facility Operating License No. DPR-7,5, is hereby amended to read as follows-l c=.

.. J

'i

. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as

. revised through Amendment No. 55, are hereby incorporated.in the license..The licensee shall operate.the facility in accordance.with.

the Technical Specifications.

3.

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

j FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler. Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

-Changes to the Technical i

Specifications Date of Issuance:

October 16, 1987

,0GC)1 PDI-2/D P.

P 2

WButler en

'cher 0[jl,/87 7/q/87 Jp/g/87 g/ b/87 w

g

{~

[

4

, :1 oq i

j

-?-

'l

'(2) Technical' Specifications and' Environmental Protection' Plan :

.j The. Technical Specifications contained in Appendices A and R, as i

revised through Amendment No. 55:. are hereby incorporated in the license.. The licensee shall operate-the facility.in accordance with the Technical Specifications.

3.

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

W

'FOR THE NUCLEAR REGULATORY' COMMISSION

.j k/h5

\\

t.

Walter R. Butler, Director '

Project Directorate I Division of. Reactor Projects I/II

Attachment:

1 Changes to the Technical Specifications 1

Date of Issuance:

october 16, 1987 i

e I

)

h_____m

1 ATTACHMENT TO LICEP:SE AMENDMENT NO. 55 l

FACILITY OPERATING LICENSE NO.' DPR-75

-l l

DOCKET NO. 50-311 Revise Appendix A as follows:

s Remove Pages Insert Paces l

)

3/4 1 3/4 1-11

)

.i 3/4 1-12 3/4 1 3/4 5-1 3/4 5-1 j

3/4 5-9 3/4 5-9 B 3/4 1-3 8 3/4 1-3 j

B 3/4 5-2 B 3/4 5-2 B 3/4 5-3 l

c l

-+.

m._-__m.___

i l' ~

1 1

l REACTIVITY CONTROL SYSTEMS BORATE 0 WATER SOURCES - SHOT 00WN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimus, one of the following borated water sources shall be OPERABLE:

a.

A boric acid storage system and at least one associated heat l'

tracing system with:

1.

A minimum contained volume of 835 gallons, 1

1 2.

Between 20,000 and 22,500 ppa of boron, and l

3.

A minimum solution temperature of 145'F.

b.

The refueling water storage tank with:

1.

A minimum contained volume of 12,500 gallons, l

2.

A minimum boron concentration of 2,300, ppm, and l

3.

A minimum solution temperature of 35'F.

APPLICABILITY: MODES 5 and 6.

c, i

ACTION:

l With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity e.hanges until at least one borated water source is restored to OPERA 8LE status, j

i SURVEILLANCE REQUIREMENTS l

i f

4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

i a.

At least once per 7 days by:

i 1.

Verifying the boron concentration of the water, j

2.

Verifying the water level of the tank, and

)

3.

Verifying the boric acid storage tank solution temperature when j

it is the source of borated water.

i i

b.

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

)

is the source of berated water and the outside air temperature is

{

less than 35'F.

)

SALEM - UNIT 2 3/4 1-11 Amerdment Ib. 55

-l a

.g

.n

.mn _

. 4

< ;rt Jj f'

'11 e.

d.

g-

,., { i, 3

- REACTIv!TY CONTROL SYSTEMS-n BORATED WATER SOURCES - OPERATING l

LIMITING CONDITION FOR OPC' ATION R

~ 3.1. 2. 6 As a minimum, the following borated water source (s) shall'be OPERABLE as required by Specification 3.1.1.2:

A boric acid storage system and at % ast one associated heat tracing a.

system with:

1.

A minimum contatud volume ob5106 gallons,-

-)l-[

g

~

2.

Between 20,000'and 22;500' ppa'of boron, and /

f' l-3.

A minimum solution tempeasture of 145'F.

b.

The refueling water storage tank with:

1.

A contained volume of between 364,500 and 400,000'gwi k er water, 2.

A boron concentration'of between 2,300 and 2,500 ppm, stit l

r 3.

A minimum solution temperature of 35'F.

,J 'i, >. 3 o

a APPLICABILITY: MODES 1,2,iand4.

J

^

ACTION:

a.

With the boric acid storage system inoperable and bein.q use'dW one

~

of the above required borated water sources, restore the stdfage.

i system to OPERA 8tE status.within 72 ho @s or be in at least HOT m STANDBY within'the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and b hated to'a SHUTDOWN MARGIN'

{

equivalent.to at least 1% delta k/k at 200*F; restore the boric acid storage system to OPERA 8LE status within the next 7 days or be in i

COLD SHUTOOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the refueling water storage tank inoperable, restore the' tank to OPERABLE status within.one hour er be in at least HOT STANOBY within the next 6 hourt'and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

.\\

SURVEILLANCE REQUIREMENTS 1

4.1.2.6 Each borated water source shall be demonstrated OPERA 8LE:

f a.

At least once per 7 dayi by:

)

1.

Verifying the boron concentration in each vtter sourca, 2.

Verifying the water level of each water source, and 3.

Verifying the boric acid storage system solution temperature.

1 b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperatur.e when the outside air temperature is less than 35'F.

3 SALEM - UNIT 2 3/4 1-12 Amen &nent p. 55 3

.,..g

, 4,,

r w

a-2- - - - - - - - - - - - "

~

T Q

g f

.rt l;

' )R,

il ll

' ll '

[.Y) -

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) j ACCUMULATORS i

t u.

LIMITING CONDITION FOR OPERATION-1 3.5.1 Each reactor coolant system accumulator shall be OPERABLE with:

a.

The isolation valve open, F

' b.

A contained volume of between'3223 and 6500 gn11ons of borated

water, c.

A boron Leoncontration of between 2200.. arid 2500 ppe, and l

a

- d.,

A nitrogen cover pressure of bie,een.595 5 and 647.5 psig.

APPLICA81LITY: MODES 1, 2 and 3.*

t ACTION:

a.

With one accumulator inoperable, except as a result of a closed isolation. valve, restore the inoperable accuplator to OPERABLE status within 'one hour or be in HOT SHUll)0WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one acetaclater inoperable due to the isolation valve being closad,t a$ther immediately open the isolation valve or be in HOT STAND 8Y vithin one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCEREQUIRfgNTS

=.

4.5.1 Each accumulator shall be demonstrated,0PERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

'1.

Verifying the water level and nitrogen cover pressure in the tanks, and J.

Verffying that each accumulator isolation valve is open.

" Pressurizer Pressu's above 1000 psig.

e '4,

s SALEM - UNIT 2 3/4 5-1 AmoMment Nb.

55

'(

l

-I' a.

.s xv;

y J

t oy

.c

]

.s $1}

q

', / '&h' g.

q l

4 a i'

g. j EMERGENCY CORE' COOLING SYSTEMS s

I REFUE LING WATER STORAGE TANK f1 d;

' y

?'O LIMITING CONDITION FOR OPERATION d a ' y) '

~

.s i

3.5.4.The refueling water storage tank l(RWST) shall be OPEPMBLE hit $:

i 3

A contained volume of betweeds64,000.and 400,000 of borated water.

.l' a.

f b.

A boron concentration of between 2,300 and 2,500 ppm, an'd l-A minimum water.temperaturtfof 35'F.

c.

APP LIC AB I LITY: M0 ES 1, 2 3 and.4

[\\

ACTION:

With the refueling water storage tank inope{rable restore the td.sk"to OPERABL status within I hour-or be in at least HOT STANCBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD-a SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . -

'6

,l q.

a

+%

i f _._.J g h

SURVEILIMCE REQUIP.EMENTS y'

i I'

y 3

1 s

4.5. 4 The RWST shal) 'pc cjegonjtrated OPERABLE:

l

[

i

/

x j

a.

At least once phr 7 days by:

-)

.,i j

t-

'l 1.

Verifying 'bf water level in the t'ank', and.

rL i

2 Verifyin i he borjn concehtratio J( t water.

(

.j.

Ah least <oncU hIr [4 hours by 'vlerifyinh TIM when the outside air temperature) Is < 357.}RWST tergeratu're b.

\\

)

[

c c

s l'

l

(

,1,i y

+a*

',, {

.g

(.

/\\' L, " /, - ]

' 'ffa 1

r i

9

}f 4,

~

\\

l

^

e

,p?

g h

Y /4 5-9 h adment No. d,.'

SA!IM - UNIT 2

',..;t 6' ;

't

.i

'n

.t

,'3 I

>t f:

4

.j f.

5 s,,

h d

I 0

\\)

4 b ' %

' tv,

t

2,, e

'i

~

4 i

REACTIVITY CONTROL SYSTEMS BASES 3/ 4.1. 2 BORhTION SYSTEMS' The boron injection system. ensures that negative reactivity. control is available during each. mode of facility operation. The-components required to

.i perform.this function include:

1) borated water sources, 2) charging pumps ? 3),.

1 separate flow paths, 4) boric acid transfer pumps, 5) associated heat tracing systems, and 6) an emergency power supply from~ 0PERAB LE. diesel' generators.

t y

With the RCS average temperature above 200'F, a minimum.of two boron j

injection flow paths are required to ensure' single functional. capability:in. the'.

event an assumed.f ailure ' renders one of L the flow paths. inoperable. The boratioq.

capability-of either flow path is sufficient to: provide a SHlRODWN. MARGIN from:

expected operating conditions of 1.6% delta k/k after xenon decay and cooldown -

to 200*F. The maximum expected boration capability ' requirement occurs at E0L-from full power equilibrum xenon conditions and requires 5106 gallons of 20,000, ppm borated water from the boric acid storage tanks or 85000 gallons of 2300 ppm

-j borated water from the refueling water storage tank..However,-to be. consistent 1

with the ECCS requirements, the RWST is required to have a minimum contained j

volume of 350,000 gallons during operations in MODES 1, 2, 3 and 4 With the RCS temperature below 200'F, one injection system is ; acceptable without single f ailure consideration on the basis of the stable' reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change.in the event the single. injection i

system becomes inoperable.

The boron capability required below 200*F is sufficient to provide a -

SHUTDOWN MARGIN of 1% delta k/k after xenon decay and cooldown from 200*F to-1 140 *F. This condition requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 12500 gallons 'of 2300 ppm borated water l

f rom the refueling water storage tank.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated.

within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limits : include allowance-for water not available because of discharge line location and other physical characteristics.

N

~.

1 The OPERABILITY of one boron injection system during REFUELING ensures that...

this system is available for reactivity control while in MOE 6.

SALEM - UNIT 2 -

B 3/4 1-3 Amen & ment No. 55 Ca

EMERGENCY CORE COOLING SYSTEMS i

BASES i

ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is i

acceptable without single failure consideration on the basis of.the stable omEtivhy condition of the reactor and the limited core cooling.

l requirements.

i The limitation for a maximum of one safety injection pump to be' OPERABLE and the Surveillance Requirement to verify all safety-i injection pumps except the allowed OPERABLE safety injection pump to be' inoperable below 312*F provides assurance that a mass addition

. pressure transient can be relieved by the operation of a single POPS relief valve.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a miniana, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.

Surveillance requirements for throttle ~ valve position stops and flow balance testing provide assurance that proper ECCS. flows will be l

maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection I

l point is necessary to:

(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level'of total ECCS flow to l

all injection points equal to or above that assumed in'the ECCS-LOCA l

analyses.

3/4.5.4 RETUELING VATER STORAGE TANK The OPERABILITY of the RVST as a part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event'of a LOCA.

The limits on RWST mininua volume and boron concentration ensure that:

(1) sufficient water is available within containment to permit l

recirculation cooling flow to the core, (2) the reactor will remain L

suberitical in the cold condition following a small LOCA' assuming-complete mixing of the RVST, RCS, and ECCS water volumes with all control rods inserted'except the most reactive control assembly I

(ARI-1), and (3) the reactor will remain suberitical in the cold condition.following a large break-LOCA (break flow area > 3.0 s4F ft.)

assuming complete mixing of the'RVST, RCS, and ECCS water and other sources of water that say. eventually reside in the sump following a LOCA with all control rods-assumed to be out (ARO).

SALEM - UNIT 2 B 3/4 5-2 knen&nent No.

55

l 4

\\

1 EMERGENCY CORE COOLING SYSTEMS j

BASES RETUELING VATER STORAGE TANK (Continued)

The limits on contained water volume and boron concentration also l

ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band ninimizes; 1

the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The j

l contained water volume limit includes an allowance for water not usable because of tank discharge line location or other' physical characteristics.

I 1

l J

.4, 1

l SALEM - UNIT 2 B 3/4 5-3 Amendment No. 55 l

.,

ML20236B211

Contents

Text

Attachment:

Attachment:

Attachment:

Attachment:

Navigation menu

ML20236B211

Text

Attachment:

Attachment:

Attachment:

Attachment:

Navigation menu

Search