ML20245C362

Amend 91 to License NPF-6,changing Tech Specs to Provide Clarification Based on Revised Reporting Requirements Affected by 10CFR50.72 & 73,per Generic Ltr 83-43

ML20245C362
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/18/1989
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245C366	List: ML20245C362 ML20245C368
References
GL-83-43, NUDOCS 8904270134
Download: ML20245C362 (57)

Text

__

)

[ga sic & %

UNITED STATES y

s.c [ j NUCLEAR REGULATORY COhlMISSION 3

• c f a WASHING TON, D. C. 20555 i

k.u c

ARKANSAS POWER AhD LIGHT COMPANY DOCKET N0. 50-368'

)

ARKANSAS NUCLEAR.ONE, UNIT 2 AMENDMENT.TO FACILITY.0PERATING LICENSE Amendment No. 91 License No. NPF 1.

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

A.

The application for arendment by Arkansas Power and Light Company (the licensec) dated November 17, 1986 and as supplemented on January 13 and April 5,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; E.

The facility will operate in conformity with the application, as ar. ended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance:

(i)thattheactivitiesauthorized by this amendment can be ccnducted without endangering the health ano safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this license amendment will r,ot be inimical to the cu mon defense and secuiity or to the health and safety of the public; and j

J E.

The issuance of this amendmene is in accordance with 10 CFR Part 51 I

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

l i

I 1

1 fg42;gggQ$[8(gge P

l c'

t

l. l 1

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment, and Paragraph 2.C.(2) of facility Operating License No.

NPF-6 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and B, j

as revised through Amendment No.91, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

' g,

[. i t -e v

/' Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 18, 1989

s I

ATTACHMENT TO LICENSE AMENDMENT.NO. 91 FACILITY OPERATING LICENSE NO. NPF-6 BCCKET.NO. 50-368 l

Revise the following pages of the Appendix "A" Technical Specifications with the attachec pages. The revised peges are identified by Arnendment nuinber ano centain vertical lines ir.dicating the areas of change. Overleaf l

l pages are provided to rr.aintain docurrent corapleteness.

REMOVE PAGES INSERT PAGES I

I XVII XVII 1-2 1-2 3/4 3-45 3/4 3-45 3/4 3-54 3/4 3-54 3/4 4-10 3/4 4-10 3/4 4-12 3/4 4-12 3/4 6-9 3/4 6-9 3/4 7-38 3/4 7-38 3/4 8-da 3/4 8-4a 3/4 11-4 3/4 11-4 3/4 11-5 3/4 11-5 3/4 11-7 3/4 11-7 1

3/4 11-10 3/4 11-10 t

3/4 11-11 3/4 11-11 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-16 3/4 11-16 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-8 3/4 12-8 3/4 12-9 3/4 12-9 B 3/4 4-3 B 3/4 4-3 6-7 6-7 6-10 6-10 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 6-17 6-17 6-18 6-18 6-19 6-19 6-19a 6-19a 6-22 6-22 I

l

4 6

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms................................................

1-1 1 5 e rm a l P ow e r................................................

1-1 Rated Thermal Power..........................................

1-1 Operational Mode - Mode......................................

1-1 Action.......................................................

1-1 Operable - Operability.......................................

1-1 Reportable Event............................................

1-2 l

Containment Integrity........................................

1-2 Channel Calibration..........................................

1-2 Channel Check................................................

1-3 Channel functional Test......................................

1-3 Core Alteration.............'.................................

1-3 Shutdown Margin..............................................

1-3 Identified Leakage...........................................

1-4 U ni d e nt i f i e d Le a ka g e.........................................

1-4 P re s s ure Bounda ry Lea kage....................................

1-4 Azimuthal Power T11t.........................................

1-4 Dose Equivalent I-131........................................

1-4 E-Average Disintegration Energy..............................

1-5 Staggered Test Basis.........................................

1-5 Frequency Notation...........................................

1-5 Axial Shape Index............................................

1-5 Reactor Trip System Response Time.............................

1-5 l

Engineered Safety Feature Response Time......................

1-6 Physics Tests................................................

1-6 Software.....................................................

1-6 Planar Radial Peaking Factor.................................

1-6 ARKANSAS - UNIT 2 I

Amen 1 ment No. f#,91 1

a

A e

- s INDEX-ADMINISTRt.TIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N.....................................

6-12 l

6.7 SAFETY LIMIT VIOLATION......................................

6-13 6.8 PROCEDURES..................................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS........................................

6-14 6.9.2 SPECIAL REP 0RTS........................................

6-19 6.9.3 SEMIANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT........

6-19a l

6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.....

6-21 6.10 RECORD RETENTION...........................................

6-22 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-23 6.12 ENVIRONMENTAL QUALIFICATION................................

6-23 6.13 HIGH RADIATION AREA........................................

6-24 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM).....................

6-25 l

ARKANSAS - UNIT 2 XVII AMENDMENT NO. 2Z, ff.91

4 s

1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2815 MWt.

OPERATIONAL MODE - MODE 1.4 An OPERATIONAL MODE (i.e. MODF) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the s component or device to perform its function (s) ystem, subsystem, train, are also capable of performing their related support function (s).

i ARKANSAS - UNIT 2 1 -1

)

I 1

L 4

DEFINITIONS

~

REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

1.8.1 All penetrations required to be closed during accident condition are either:

Capable of being closed bv an OPERABLE containment a.

.i automatic isolation valve system, or b.

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.

1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is OPERABLE pursuant to Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.

~

CHANNEL CALIBRATION

1. 9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output, such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

ARKANSAS - UNIT 2 1-2 Amendment No.91

4 INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

APPLICABILITY: During releases via this pathway.

ACTION:

With the following gaseous effluent monitoring in-a.

strumentation channels alarm / trip setpoint less con-servative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel.

1.

Waste Gas Holdup System Noble Gas Activity Monitor.

(during periods of gaseous releases.)

2.

Containment Purge and Ventilation System Noble Gas Activity Monitor.

(during periods of containment building PURGE.)

b.

With less than the minimum number of monitoring instrumentation channels OPERABLE, take the action shown

)

in Table 3.3-12, Return the instruments to OPERABLE status within 30 days c.

or, in lieu of any other report, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected.

d.

The provisions of Specifications 3.0.3, 3.0.4, and 4.0.4 l

are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous affluent monitoring instruments-tion channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-12.

ARKANSAS - UNIT 2 3/4 3-45 Amendment No. 68.91 l

9 NO 2,

I 5

6 7

8 8

6 6

T 2

2 2

2 2

2 2

CA f

f o

a e

e c

c y

y n

n t

t e

e w

N w

i s

s w

o i

O v

o v

e e

o l

I R

i l

i re r

l F

T E

t F

t Pg P F

A T

c c

d r

T E

a m

a yi yr m

e N

M o

e o

f r f e e

l E

A i

t i

t t it t

p M

R d

s d

rr rl s

m U

A a

y a

ea ei y

a R

P R

S R

VC VF S

S T

SN Y

I T

I G

L N

I I

8 R

A

^

O C

T I

2 I

L 1

N P

O P

3 M

A 3

TN SE E

E MLL t

U UEB 8

L MNA A

F I

NR 1

1 1

1 1

1 1

T F

NAE l

E I iP MCO S

~

U m

O e

E t

S s

A y

G S

E c

n V

i r

o r

I t

o i

o T

ra t

t r

r t

'l C

om i

a o

e i

A t o n

l t

e t

n D

it) o i

i g

l o

I nue M

t n

d i

M O

oas n

o i F

A M

a w

e M

r w

r R

m de o

V t

r o

e e

ynl y

r e

l t

l t

t ae F

d t

a l

F t

s i

r n

C p

n i

y vm m

a v

m m

o S

irf e

i r

a e

M tao t

e t

e S

t p

cl s

g c

l s

w u

Aan y

r A

p e

y o

d o

S u

m t

S l

l ssi P

s a

a F

o aet t

a S

l t

H Gda n

t G

u n

r T

in e

n e

c e

e N

s evi u

e e

n i

u l

E a

l om l

m l

i t

l p

i M

G brr f

n b

d r

f m

U ope f

i o

o a

f a

R e

N(t E

a N

I P

E S

T t

t S

s n

N a

o I

W a

b C

a b

c d

e 1

2 ghy{

m g yg F.

aE5

. TABLE 4.3-12 (Continued)

TABLE NOTATION

• During releases via this pathway.

• • A SOURCE CHECK is not required if the background activity is greater than the activity of the check source.

i (1) During Containment Building ventilation operations.

(2) Verify presence of cartridge or filter only.

O l

l i

ARKANSAS - UNIT 2 3/4 3-53 Amendment No. 60 1

I

i s

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip set-points set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

APPLICABILITY: During releases via this pathway.

ACTION:

With a radioactive liquid effluent monitoring instrumentation a.

channel alarm / trip setpoint less conservative than required by the above specification, immediately suspended the release of radioactive liquid effluents monitored by the affected channel, until the set point is changed to an acceptable conservative

value, b.

With less than the minimum number of monitoring instrumentation channels OPERABLE, take the action shown in Table 3.3-13.

Return the instruments to OPERABLE status within 30 days or, c.

in lieu of any ot5er report, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected.

d.

The provisions of Specifications 3.0.3, 3.0.4, and 4.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each. radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-13.

ARKANSAS - UNIT 2 3/4 3-54 Amendment No. 68.91 i

i

s REACTOR COOLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.

Ar. used in this Specification 1.

Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indica-tions below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2.

Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3.

Degraded Tube means a tube containing imperfections 20%

of the nominal wall thickness caused by degradation.1 4.

% Degradation means the percentage of the tube wall thick-ness affected or removed by degradation.

5.

Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

6.

Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.

7.

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c. above.

8.

Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

ARKANSAS - UNIT 2 3/4 4-g o

4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9.

Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes cortaining through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports Following each inservice inspection of steam generator tubes, a.

the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed.

This report shall include:

1.

Number and extent of tubes, inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged, i

c.

Resu,lts of steam generator tube inspections which fall into 1

Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Table 4.4-2.

Notification of the Commission will be made prior to resumption of plant operation.

The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

i 1

ARKANSAS - UNIT 2 3/4 4-10 Amendment No. 91

il l

I

)

s a

s s

r n

o o

t mi m

at ut ra eci eh brd gnt in ne eyco m

igema c

t t omh amas ce t ac sur o ei r r s e i

rtdeo v

s o

e e

sndt re e

w n

n a

inaes Y

T O

O f

urd nos ent o

ntnUs roae o

r eih g.m obtt E

t mc mse BN aueearh O

rnpteot OI e

sott TT nenNsat C

ehi rc SE gt

.eee rnp RP s

OS msuroes TN aioemgn AI e

in i

R tNvnrm EE s

eaoao NC erm et 1

EI erp et GV ne ensd R

ohrko e

4 ME woi ri 4

AS o(

l nef EN t

t ihi E

TI ssa td L

S der soo B

G ebinn m

A FN t ufion T

OI s

it iie R

n m

e gt b

RU o

i eh ni e ED i

lhtidsl B

t t

mnol MD c

e f roha UE e

bfoocth NT p

o f

s C

s y

srgn m%tenae ME t

n a

l pi h c UP i

I MS n

Nu ttn I N U

e n

sea e

NI c

o3erreu I

r i

i raerq M

e n

v tg pee p

o r

cnesovs i

e eihr e

s t

s pstoese r

c n

ss th l

n o

e I

nafatep o

t p

i pi r rm i

a s

t m

e,oa t

r n

n eo) nsms c

e I

e cctee e

n u

inngcee p

e e

q vea nbh s

G c

e n

r l ma t

n i

s o

eepato I

m v

b i

sl ests a

r u

t nuetm e

e e

e S

a idhsudc c

t s

t et cnn i

S n

o eh l rua v

I N

hcnli ot r

f d

Tsiacfs e

o t

n e

s s

o l

e r

c b

r o

i e

a P

N F

S T

1

> j z 5,v

• xM o w14i" e

e

s g

e t

b rs n

u or i

t fi r

d u

f e

e n

d r

v of i

i i o d

u t

t e

q c

ct t

e e

al c

R f

u e

N A

A i

ms A

A A

A s

p O n /

/

d r ee /

/

/

/

n I o N

N orl N

N N

N i

Ti eg f

p Ct nu r3 m E c ol e-a s

.. PA NP PCs r

. a o

ta r

, T e

L n

P e

M g

A t m

Sle a

t e

D s A

A 1 2 3

A A

A A

t R e

/

/

/

/

/

/

s 3 R N

N CC C

N N

N N

f la sng.

o d

n r

eo.

t n

g e

i i

d i 5 rs ro u

h i t or oc sl n

ti s fi f e ep a

d di f

s h

s tn e

edh n

n id et e

N r

vat of of t n b r e

O i

i i

o i o a uo I

u tt n t

t h

l t p 2

T q

cci ct ct l

eR e9 s

t er C

e e

ee al e

al aG E

R A

n f ps u

n u

v p

i P

/

o es e ms o

ms t.

il 6

S N n N

N d

I I i gin b, ree N

re e

c5 t aC n

N O o i

f p

f p

ph ecN c d

orl or l

e ciR.

n t

2 T t E

C c lid r3 m r2 m

s c f e e

n n5 e-a e-a na epop a

4 im EA P a4 PCs PC s

I e dStS P

4 T

S E

R I

i N

t L

O 3

n A

A e

s.

u B

T E.

o l

l C o

T R

Pl rr Gn a

a e

ea ne ns h

L M

h

.t or oI t

N At E

Sl s.

S u ia i

t G

ti o

b id G.3 d

t t

G e

iG.

n D s A

1 2

3 l

i 1

m2 M

N e /

l o-d d

A 2R M

C C

C A5C SC a5C A5 r

s E

T o

S l

ta a.

r s n G.

n eo e

bi5 i -

n ut sdd i 2

n e

e 9

g ti s c

ns d

di igae.

t 6

m e

edh dii n

i G.

a r

vat tl si d

r n

e i

i pet 5 o

o t

u tt n

,b p

l i

q cci l

s u5 r ert e

e ee a

.t2 e R ea f

R n

f ps G. e t t h

pc o

o es e t

l i

n N

d nb c5 vco aCf r

o iu e i e iRi en i

g t

pst ph cN c b o t

ud sics c e

e imi c

l n5 nhena pop t t A

Pa2 I tfi e StS nc e

ep t

h s Nl t n Ou i

s I s 1

2 3

T e i n CR C

C C

a E

N P

g S

en N

ri I

f er e

or h u i e Wd E

L iz up PS t

M ns A e ie Sl sb p

iuG.

3 T m mT S a I S A55 5

>:h5g. e2y g wg 34t 3

3 x

o

i CONTAINMENT SYSTEMS SURVEftla CE REQUIREMENTS (Continued) 4.6.1.5.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Specification 4.6.1.6.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages. ' Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.

4.E 1.5.3 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of these surfaces and verifying no apparent changes in appearance or other abnormal degradation.

4.6.1.5.4 Deleted ARKANSAS - UNIT 2 3/4 6-9 Amendment No. 91 1

4 PLANT SYSTEMS 3/4.7.11 PENETRATION FIRE BARRIERS LIMITING CONDITION FOR OPERATION 3.7.11 All penetratieri fire barriers protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

a.

With one or more of the above required penetration fire barriers non-functional, establish a continuous fire watch on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11 The above required penetration fire barriers shall be verified to be functional:

a.

At least once per 18 months, b) a visual inspection, b.

Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

i ARKANSAS - UNIT 2 3/4 7-37

4 PLANT SYSTEMS 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPEDATION 3.7.12 The structural integrity of the spent fuel pool shall be maintained in accordance with Specification 4.7.12.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

With the structural integrity of the spent fuel pool not a.

conforming to the above requirements, in lieu of any other report, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days of a determination of such non-conformity.

i b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.12.1 Inspection Frequencies - The structural integrity of the spent fuel pool shall be determined per the acceptance criteria of Specification 4.7.12.2 at the following frequencies:

At least once per 92 days after the pool is filled with water.

If a.

no abnormal degradation or other indications of structural distress are detected during five consecutive inspections, the inspection interval may be extended to at least once per 18 j

months.

b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following any seismic event which actuates or should have actuated the seismic monitoring instrumentation of Specification 3.3.3.3.

4.7.12.2 Acceptance criteria - The structural integrity of the spent fuel pool shall be determined by a visual inspection of at least the interior and exterior surfaces of the pool, the struts in the tilt pit, the surfaces of the separation walls, and the structural slabs adjoining the pool walls.

This visual inspection shall verify no changes in the concrete crack patterns, no abnormal degradation or other signs of structural distress (i.e, cracks, bulges, out of plumbness, leakage, discolorations, efflorescence, etc.).

1 ARKANSAS - UNIT 2 3/4 7-38 Amendment No.91

r 1

i l^

i 1

f 1

i ELECTRICAL POWER SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued)

_m 10.

Verifying that the auto-connected loads to each diesel I

generator do not exceed the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 3135 kw.

11.

Verifying the diesel generator's capability to:

1 a)

Synchronize with the offsite power source while the i

generator is loaded with its emergency loads upon i

a simulated restoration of offsite power, b)

Transfer its loads to the offsite power source, and c)

Proceed through its shutdown sequence.

12.

Verifying that with the diesel generator operating in a test mode (connectec to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to standby operation and (2) auto-matically energizes the emergency loads with offsite power.

13.

Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross connection lines, d.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 900 rpm in < 15 seconds.

4.8.1.1.3 Reports - See Specification 6.9.1.5.d.

l t

l ARKANSAS - UNIT 2 3/4 8-4a Amendment No.91

1

\\

' )

1 I

TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures In Last 100 Valid Tests

• Test Frequency 1 1 At least once per 31 days 2

At least once per 14 days i

3 At least once per 7 days

?4 At least once per 3 days

• Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1. August 1977, where the last 100 tests are determined on a per nuclear unit basis. For the purposes of this test schedule, only valid tests conducted after the Operating License issuance date shall be included in the computation of the "last 100 valid tests". Entry into this test schedule shall be made at the 31 day test frequency.

I I

l l

t ARKANSAS - UNIT 2 3/4 8-4b O

TABLE 4.11-1 (Continued)

V is the sample size (in units of mass or volume).

2.22 is the number of transformations per minute per picocurie.

Y is the fractional radiochemical yield (when applicable).

A is the radioactive decay constant for the particular radio-nuclide, and i

at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

Typical values of E. V, Y, and At shall be used in the calculation.

It should be recognized that the LLD is an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

For ce'tain mixture's"of gamma emitters, it may not be possible to b.

r measure radionuclides in concentrations near their sensitivity I

limits when other nuclides are present in the sample in.much greater l

{

concentrations. Under these circumstances, it will be more j

appropriate to calculate the concentration of such radionuclides

]

using observed ratios with those radionuclides which are measurable, l

c.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

l d.

A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling, each batch shall be isolated and mixed to assure representative sampling.

/

e.

The principal gamma emitters for which the LLO specification will apply are exclusively the following radionuclides: Mn54, Fe59 CoSB, Cc60, In65, MoS9, Cs134, Cs137, Cel41, and Ce144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiabit, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual i

circumstances result in LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.

ARKANSAS - UNIT 2 3/4 11-3 Amendment No. 60 l

4 a

' RADIOACTIVE EFFLUENTS DOSE.

LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose commitment to a MEMBER OF THE PUBLIC.from radioa'ctive

' materials in liquid effluents released from AND-2 to the discharge canal

.shall be limited:

.During any calendar. quarter to less 'than or equal to 1.5 mrem to a.

the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above' limits, in lieu of any other report submit a Special Report pursuant to Specification 6.9.2.h within 30 days.

b.

The provisions.of specifications 3.0,3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the 00CM at least once per 31' days.

ARKANSAS - UNIT 2 3/4 11-4 Amendment No. 66.91

__-___ = _ _ -

~

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3. The LIQUID RADWASTE TREATMENT SYSTEM shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from ANO-2 to the discharge canal, would exceed.18 mrem to the total body or.625 mrem to any organ in any calendar quarter.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged without treatment a.

and in excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days in accordance with the ODCM.

t ARKANSA5 - UNIT 2 3/4 11-5 Amendment No. 55,91

RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS

• LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each unprotected outside temporary radioactive liquid storage tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material exceeding the above limit, immediately suspend all additions of radioactive material to the affected tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applica'le.

o SURVEILLANCE REQUIREMENTS 4.11.1.A The quantity of radioactive material contained in each unprotected outside temporary radioactive liquid storage tank shall be determined to be within the above limit by analyzing a representative sample of the contents of cche tank at least once per 7 days when radioactive materials.are being added to the tank.

I

• Tanks included in this Specification are those outdoor temporary tanks that do not have 1) liners, dikes or walls capable of holding the tank contents, or 2) tank overflows and surrounding area drains connected to the LIQUID RADWASTE TREATMENT SYSTEM.

ARKANSAS - UNIT 2 3/4 11-6 Amendment No. 60

a 4

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents.from the site to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the following:

a.

For noble gases:

Less than or equal to the 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.

b.

For iodine-131, for tritium and for all radionuclides in particular form with half-lives greater than 8 days:

Less than er equal to 1500 mrem /yr to any organ.

During periods of containment purging the dose rate may be averaged over a one hour interval.

APPLICABILITY:

At all times.

ACTION:

With the dose rate (s) exceeding the above limits, without delay a.

restore the release rate to comply with the above limit (s).

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

l applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of'the ODCM.

4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half-lifes greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing enalyses in accordance with the sampling and analysis program specified in Table 4.11-2.

l l

I 1

l i

i ARKANSAS - UNIT 2 3/4 11-7 Amendment No. fB. 91 l

I{II!liI1lIIlIIItgiIIIlliIIIIIIIIIll

)

)

f 0 ol v

tg I

I I

i 9

9 9

u i

I I

I mn q

2 e

i o)

• 8 4 8 1

Lil

- 3 t m 0

00 00 0

0 0

0 03 r c/

1 11 1 1 1

1 1

1 11 eei wtC x

xx xx x

x x

x xe ceu X

tD(

1 11 1 1 1

1 1

1 1(

IIII IiII li1I iIlI l1II lill liII ilIiI iII

)

)

)

I b

b b

D

(

(

(

I M

s s

s s

A r

r r

r R

e e

e e

G t

t t

t O

t t

t t

R i

i i

i P

m m

m m

s E

E E

E s

S e

s E

s a

a a

a) o S

y m

m n

n s r

Y l

m m

n a r Ga s

u L

a a

a a

ae 0

n A

n G

G G

Gh a

9 s su N

fA t

h ea A

o l

l l

l O p

r sG y

a a

a a

l a

D et p

p p

p,

a Gr N

pi i

i i

i1 o

A yv c

c c

1 c3 s

9 e

Ti n

n n

3 n1 s

8 l a G

t i3 i3 1

i -

o bt i

2 N

c r

r -

r-rI r

r oe I

A P

PH PH I

P(

G S

MB 1

L 1

P il 1IilI1 lilIillIllII ll1l iiiI li1II liI M

4 A

e e

e e

S k

g l

t t

t E

y n

r a

a a

ei s

L E

sc a

u

) oe

)l l

tl a

B T

men T

P f cl f u u

u Gr i

A S

us e P

P

?

( rp

( ce ce sce o

T A

myu h

h am Mil Qoil et il W

q c

c Wh a Wt p t p pt p i lnae a

a CS rm rm a rm bn l i S

nr E

E aa aa eaa oo i

U MAF PS PS CPS NM O

E S

liiIlliI lilIIIlI IlII IIIl iiII IllII lII AG I

I

)

I I

e g

E l

e e

I I

V y

kp el l

s s

s s

s I

I I

gc nm gp

) p u

u u

u u

T nn aa r m dm o

o o

o o

C i e PTS ua

( a u

u u

u u

A l u PPS S

n n

n n

n 0

pq hb

)

i i

i i

i 1

m e ca hb cb t

t t

t t

0 ar ar ca

( a n

n n

n n

A SF EG ar r

o o

o o

o R

EG MG C

C C

C C

l1II Illl IIlI IilIllII1iIIIIlIIlIIIIlI

)

) -

ni t

ot e i x

)

i n t

t ep E. l n t e s) n o

aV ege y

goi i

wnV T

dot t a di k

g 1 Pa t e adt e

n d

8 l

nr Rl s s

a l

li eA i

im a

sT B

s yet V. e l ue e

a t

run eBh l

Ge r

n aF e gt v

x e

g o

e i V

ds) eeE)

R ea t e V

l t 1 en Lg n

t r cg ina 8wo

- aCo s

so ar t

xee di wrAi u

at eu i

upr xat ooVt o

WS RP n

ASA RRa LtHa e

U

((

((l (S(l sa G

A 8

C IiIiIlll1llIIlllIllIIIIllIIIIlIIIilI

$gvC. eE* "

t'

• Z a kn* k 2 5* %

TABLE 4.11-2 (Centinued)

TABLE NOTATION a.

The Lower Limit of Detection (LLD) is defined in Table Notation a.

of Table 4.11-1 of Specification 3.11.1.1.

b.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe 59, Co-58. Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyset should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be cocumented in the semiannual effluent report.

c.

Tritium greb samples shall be taken from the Reactor Building ventilation exhaust at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

d.

Tritium grab samples shall be taken at least once per 7 days' from the ventilation exhaust from the spent fuel area, whenever spent fuel is in the spent fuel pool, e.

The ratio of the sample flow rate to the sampicd stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specification 3.11*2.1, 3.11.2.2, and 3.11.2.3.

f.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from the sampler).

y g.

For certain radionuclides with low gamma yield or low energies, or for certain radionuclides mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-stances, the LLD may be increased inversely proportional to the magnitude of the gamma yield (i.e., 1 x E-4/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this sanner for a specific radionuclides, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix 8, Table II, Column I.

ARKANSAS-UNIT 2 3/4 11-9 Amendment No. 60 1

6

4 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.21 The dose due to noble gases released in gaseous effluents from ANO-2 to UNRESTRICTED AREAS (See Figure 5.1-3) shall be:

'a During any calendar quarter, less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for l

beta radiation, aad b.

During any calendar year, less than or equal to 10 mrads for gamma radiation and less than or. equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from radioactive noble gases'in gaseous a.

effluents exceeding.any of the above limits, in lieu of any.other report, submit a Special Report pursuant to Specification 6.9.2.h'

.within 30 days b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dese Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

ARKANSAS - UNIT 2 3/4 11-10 Amendment No. 58.91

RADI0 ACTIVE EFFLUENTS DOSE - 10 DINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION F0D OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from ANO-2 to UNRESTRICTED AREAS (see Figure 5.1-1) shall be:

During any calendar quarter, less than or equal to 7.5 mrems to a.

any organ, and b.

During any calendar year, less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of iodine-131, tritium, a.

and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.

b.

The provisions of Specifications 3.0.3 and.3.0.4 are not I

applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.

Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.

ARKANSAS - UNIT 2 3/4 11-11 Amendment No. 66,91

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses from ANO-2 to UNRESTRICTED AREAS (see Figure 5.1-1) would exceed.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter; or when the projected doses due to iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days would exceed 1.0 mrem to any organ over a calendar quarter.

APPLICABILITY: At all times.

j ACTION:

With gaseous waste being discharged without treatment and in a.

excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS q

l 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected j

at least once per 31 days in accordance with the ODCM.

j 1

l i

)

ARKANSAS - UNIT 2 3/4 11-12 Amendment No. 68 91

i RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR ODERATION 3.11.2.5 When degasifying the reactor Coolant system, the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive material in gaseous waste prior to their discharge when the projected gaseous effluent doses for ANO-2 to UNRESTRICTED AREAS (see Figure 5.1-1) would exceed.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter.

APPLICABILITY: At all times.

ACTION:

With gaseous waste being discharged without treatment and in a.

excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

ARKANSAS - UNIT 2 3/4 11-13 Amendment No. 69 91

/

+

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 300,000 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, imediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank and the reactor coolant activity exceeds the limits of Specification 3.4.8.

i

)

l l

J l ARKANSAS-UNIT 2 3/4 11-14 Amendment No. 6,0 1

RADIOACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.3 The calculated doses from the release of radioactive materials in liquid or gaseous effluents shall not exceed twice the limits of Specifica-tions 3.11.1.2.a. 3.11.1.2.b. 3.11.2.2.a. 3.11.2.2.b. 3.11.2.3.a. or 3.11.2.3.b.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated doses exceeding the above limits, prepare and submit a Special Report pursuant to 10 CFR Part 20.405c.

b.

If the limits of 40'CFR 190 have been exceeded, obtain a variance from the Commission to permit further releases in. excess of 40 CFR 190 limits. A variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 4.11.3.

Dose Calculations. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

i l

l i

ARKANSAS - UNIT 2 3/4 11-15 Amendrent No.60

RADIOACTIVE EFFLUENTS 3/4.11.4 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR ODERATION The solid radwaste system shall be used in accordance with'a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and 3.11.4 burial ground requirements.

APPLICABILITY: At all times.

ACTION:

With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged a.

solid radioactive wastes from the site.

The provisions of Specifications 3.0.3 and 3.0.4 are not b.

applicable.

SURVEILLANCE REQUIREMENTS Proper solidification of wet radioactive waste shall be verified in accordance with the surveillance requirements of the Process Control 4.11.4 Program.

Amendment No. #5.9) 3/4 11-16 ARKANSAS - UNIT 2

^

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRt.M LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pursuant to the requirements of Table 3.12-1 and 3.12-2.

The sample locations shall be shown in Table 4-1 in the ODCM.

APPLICABILITY:

At all times.

ACTION:

With the radiological environmental monitoring program not being a.

conducted as specified in Table 3.12-1, prepare and submit to the Commissioned in the Annual Radiological Environmental Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

(Deviations are permitted from the required sampling schedule if specimens are not obtainable-due to hazardous conditions, seasonal unavailability, or to malfunction of sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period).

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 3.12-3 when averaged over any calendar quarter, prepare and submit to the Commission, within 30 days from the er.d of the affected quarter, a Special Report which includes an evaluation of any release l

conditions, environmental factors or other aspects which caused the limits of Table 3.12-3 to be exceeded, and defines the actions taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one of the radionuclides in Table 3.12-3 are detected in the sampling medium, this Special Report shall be submitted if:

l Concentration (1)

. Concentration (2)

....... > 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-3 are detected and are the result of plant effluents, this Special Report shall be l

submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2,.3.11.2.2 and 3.11.2.3.

This Special Report is not required

[

if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.

ARKANSAS - UNIT 2 3/4 12-1 Amendment No. 68,91

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

With milk or fresh leafy veoctable samples unavailable from any c.

of the sample locations req ired by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental mon!toring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Identify the causes of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the

' report a revised table for the ODCM reflecting the new location (s).

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The results of analyses performed on the radiological environmental monitoring samples shall be summarized in the Annual Radiological Environ-mental Report.

l j

3 ARKANSAS - UNIT 2 3/4 12-2 Amendment No. 68.91

1 l

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS l

LIMITIN^ CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest I

garden" of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated dose commitment due to I-131, tritium, and radio-i nuclides. in part iculate form greater than the values currently j

being calculated in Unit 2 Specification 4.11.2.3, submit lo-cation description in the Semiannual Radioactive Effluent Release Report per Specification 6.9.3.

b.

With a land use census identifying a location (s) which yields a calculated dose commitment (via the sample exposure pathway) greater than at a location from which samples are currently being obtained in accordance with the Specification 3.12.1, identify the new location in the Semiannual Radioactive Effluent Release Report per Specification 6.9.3.

The new location shall be added to the radiological environmental monitoring program within 30 days, if possible.

The sampling location having the lowest calculated dose commitment (via the same exposure pathway) may be.

deleted from this monitoring program after October 31 of the year in which this land us9 census was conducted.

c.

The provisions of specifications 3.0.3 and 3.0.4 are not l

applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the land use census shall be included in the Annnual Radiological Environmental Report.

ARKANSAS - UNIT 2 3/4 12-8 Amendment No. 68 91

4 RADIOLOGICAL ENVIRONMENTAL MONITORIhG 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of the Interlaboratory Comparison Program which has been approved by NRC.

APPLICABILITY:

At all times.

ACTION:

With analyses not being performed as required above, report the a.

corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not i

applicable.

SURVEILLANCE PEOUIREMENTS I

4.12.3 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be ir:1uded in the Annual Radiological Environmental Report.

ARKANSAS - UNIT 2 3/4 12-9 Amendment No. 58 91

1 l

i i

REACTOR COOLANT SYSTEM i

BASES Wastage-type defects are unlikely with proper chemistry treatment of

)

the secondary coolant.

However, even if a defect should develop in sevice,

{

it will be found during scheduled inservice steam generator tubes examinations, j

Plugging will be required for all tuts with imperfections exceeding the l

plugging limit of 40% of the tube nominal wall thickness.

Steam generator 1

tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20%'of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection f

fall into Category C-3 certain results will be reported in a Special Report to the Commission pursuant to Specification 6.9.2 as denoted by Table 4.2-2.

Notification of the Commission will be made prior to resumption of plant operation.

Such cases l

will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current l

inspection, and revision of the Technical Specifications, if necessary.

j l

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE f

1 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS l

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.

These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems" May 1973.

3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowances for a limited amount of leakage from known soruces whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The Surveillance Requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be considered as a portion af the allowed limit.

ARKANSAS - UNIT 2 8 3/4 4-3 Amendment No.91 Ofddf dd ud 6/20/81

• b

.G*

... t

, REACTOR COOLANT SYSTEM BASES The total steam generator tube leakage limit of 1 GPM for all steam generators ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. The 0.5 GPM leakace limit per steam generator ensures that steam generator tube integritfs maintained in the event of a main steam lin9 rupture or under LOCA conditions.

PRESSURE BOUNDARY LEAXAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presence cf any PRESSURE BOL":':ARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduce the.

potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits pmvides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels.in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a si.ificant effect on the structural integrity S

of the Reactor Coolant System. The time interval permitting continued operation witiin the restrictions of the Transient Limits pmvides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that con-centrations in excess of th6 limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a ARXANSAS - UNIT 2 B 3/4 4-4

i ADMINISTRATIVE' CONTROLS

. f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential nuclear safety

-l

hazards, h.

Performance of special reviews, investigations or analyses, and

]

reports thereon as requested by the Executive Director, Nuclear

)

Operations or the Safety Review Comittee.

i.

Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Executive Director, Nuclear Site Operations and the Safety Review Comittee.

j.

Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Executive Director, Nuclear Operations and Safety Review Comittee.

k.

Review of changes to the Offsite Dose Calculation Manual and Process Control Program.

AUTHORITY 6.5.1.7 The Plant Safety Comittee shall:

a.

Recommend in writing their approval or disapproval of items considered under 6.5.1.6(a) through-(d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Nuclear Operations and the Safety Review Committee of disagreement between the PSC and the Executive Director, Nuclear Operations; however, the Executive Director, Nuclear Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS

6. 5.1. 8 The Plant Safety Comittee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of all PSC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the Executive Director, ANO Site Operations and Chairman of the Safety Review Committee.

ARKANSAS-UNIT 2 6-7 Amendment No. 5, 17, 25, 52, if, 73, 55,91 l

}

ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The Safety Review Comittee shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear' engineering

)

chemistry and radiochemistry c.

d.

metallurgy e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 The $afety Review Comittee shall be corrposed of a Chairman and

)

~

eight members which collectively have the experience and I

competence required by ANSI /ANS-3.1-1981 to review problems in the areas specified in Section 6.5.2.1, a-h.

The Vice President Nuclear Operations shall designate, in I

writing, the Chairman and all SRC members.

{

i The Chaiman shall designate in writing, the alternate Chairman j

in the absence of the SRC Chairman, j

i I

1 i

I!

ARKANSAS - UNIT 2 6-8 Amendment No. 5. 27. 25. 51, 73

l I

ADMINISTRATIVE CONTROLS ALTERNATES i

6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two I

alternates shall participate as voting members in SRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as detemined by the SRC Chairman to provide expert advice to the SRC.

MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 The minimum quorum of the SRC necessary for the perfonnance of the SRC review and audit functions of these technical specifications shall consist of the Chairman or his designated altemate and at least 4 SRC members including altemates. No more than a minority of the quorug shall have line responsibility for operation of the unit.

l e

ARKANSAS - UNIT 2 6-9 4

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The SRC shall review:

The safety evaluations for 1) changes to procedures, equipment or a.

systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b.

Proposed changes to procedures, equipment or systems which. involve -

an unreviewed safety question as defined in Section 50.59, 10 CFR.

Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59, 10 CFR.

d.

Proposed changes to Technical Specifications or this Operating License.

Violations of codes, regulations, orders, Technical e.

Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g.

.All REPORTABLE EVENTS pursuant to Specification 6.6.1.

h.

.All recognized indications of an unanticipated. deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safey.

i.

Reports and meetings minutes of the Plant Safety Committee.

j.

Proposed changes to the ODCM and PCP.

l ARKANSAS - UNIT 2 6-10 Amendment No. 68. 91 lu_____-.____-------_--

l I

L ADMINISTRATIVE CONTROLS

, AUDITS 6.5.2.8 Audits of unit activities shall be perfomed under the cognizance t

of the SRC. These audits shall encompass:

l a.

The confomance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training, and qualifications of the entire unit staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.

d.

The perfomance of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix "B",

at least once per 24 months, e.

The Facility Emergency Plan and implementing procedures at least once per 12 months.

f.

The Facility Security Plan and implementing procedures at least once per 12 months.

g.

Any other area of unit operation considered appropriate by the SRC or the Vice President, Nuclear Operations.

h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection fim.

j.

The Offsite Dose Calculation' Manual and Process Control Program and implementing procedures at least once per 24 months.

k.

An inspection and audit of the fire protection and loss prevention procram shall be perfomed by a cyslified outside fire consultant at least once per 36 months.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Nuclear Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

ARKANSAS - UNIT 2 6-11 Amendment No. II.25,

1. 1,52,59,73

4 ADMINISTRATIVE' CONTROLS RECORDS 6.5.2.10. Records of SRC activities shall be prepared, approved and distributed as indicated below; Minutes of each SRC meeting shall be prepared, approved and a.

forwarded to the Vice President, Nuclear Operations within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7'above, shall be prepared, approved and forwarded to the Vice President, Nuclear Operations within 14 days following completion'of the review, Audit reports encompassed by Section 6.5.2.8 above, shall be c.

forwarded to the Vice President, Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

A report shall be submitted to the Commission pursuant to the a.

requirements of Section 50.73 to-10CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by.the PSC and, the results of this review shall be submitted to the SRC and the Vice President, Nuclear Operations by the Director, Site Nuclear Operations.

l ARKANSAS - UNIT 2 6-12 Amendment No. ZZ, 27, 25, 52, 73*91

ADMINTSTRATfVE CONTROLS 6.7 SAFETY L2MfT Vf0LATION 6.7.1 The following actions shall be taken in the event a Safety Limit is i

violated:

1 a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The Vice President, Nuclear and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

The Nuclear Regulatory Commission shall be notified pursuant to 10CFR50.72 and a report submitted pursuant to the requirements of 10CFR50.36 and Specification 6.6.

6.8 PROCEDURES l

6.8.1 Written procedures shall be established, implemented and maintained j

covering the activities referenced below-

)

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation, i

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable j

Constants. These procedures should inc1W provisions to assure that sufficient margin is maintained in CR Type I addressable i

constants to avoid excessive operator intt ;ction with the CPCs

{

during reactor operation.

1 NOTE:

Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be performed in accordance with the most recent version of "CPC Protection Algorithm Software Change Procedure," CEN-39(A)-P that has been determined to be applicable to the facility.

Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

l l

h.

New and spent fuel storage.

l 1.

00CM and PCP implementation, j

j.

Postaccident sampling (includes sampling of reactor coolant, j

radioactive iodines and particulate in plant gaseous effluent,

)

l and the containment atmosphere).

l 6.8.2 Each procedure of 6.8.1 above, the changes thereto, shall be l

reviewed by the PSC and approved by the Executive Director, ANO Site l

Operations; Plant Manager or responsible General Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

1 ARKANSAS-UNIT 2 6-13 Amendment No. 24, 28, #3, 52, 58, 53, 73, 77, 85,91 I

\\

l

)

ADMINISTRATIVE CONTROL 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the original procedure'is not altered, b.

The change is approved by two members of the plant management

, staff, at least one of whom holds a Senior Reactor Operator's

' License on the unit affected.

c.

The change is documented, reviewed by the PSC and approved by the Executive Director, AND Site Operations; Plant Manager or responsible General Manager within 14 days of implementation.-

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS j

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Administrator of the Regional Office unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing-shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed, l

ARKANSAS-UNIT 2 6-14 Amendment No. 5, 52, n, 85,91

ADMINISTRATIVE CONTROLS ANNUAL REPORTS 1 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

1 6.9.1.5 Reports required on an annual basis shall include:

A tabulation on an annual basis for the number of station, utility a.

and other personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated man rem exposure according to work and job functions,2/ e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (cescribe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functionr.

b.

The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

Documentation of all challenges to the pressurizer safety valves.

c.

d.

A diesel generator data report which provides the number of valid tests and the number of valid failures for each diesel generator.

1/

A single submittal may be made for a multiple unit station.

The submittal,should combine those sections that are common to all units at the station.

2/

This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

I 1

I ARKANSAS - UNIT 2 6-15 Amendment No. 5 KZ,91

)

1 I

l J

- =_

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT l

6.9.1.6 Routine reports of operating statistics and shutdown experience-shall be submitted on a monthly basis to the Director Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional. 0f fice no later. than the 15th of each month following

~

the calendar month covered by the report.

6.9.1.7 Deleted 6.9.1.8 Deleted I

j l

ARKANSAS - UNIT 2 6-16 Amendment No. 52.91

)

l 1i i

ADMINISTRATIVE CONTROLS l

l (text deleted)

Page left blank intentionally 6.9.1.9 Deleted ARXANSAS - UNIT 2 6-17 Amendment No, 52.91

ADMINISTRATIVE CONTROLS 9

(text deleted)

Page left blank intentionally ARKANSAS - UNIT 2 6-18 Amendment No. 52, 58.91

e ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

ECCS Actuation, Specifications 3.5.'2 and 3.5.3.

a.

b.

Inoperable Seismic Monitoring Instrumentation, Specifica-tion 3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation, Specifica-c.

tion 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

Inoperable Fire Detection Instrumentation, Specification 3.3.3.8.

e.

f.

Inoperable Fire Suppression Systems, Specifications 3.7.10.1 and 3.7.10.2.

g.

Primary coolant specific activity, Specification 3.4.8.

h.

Radioactive Effluents, Specifications 3.11.1.1, 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.2.5, and 3.11.3.

This report shall include the following:

1)

Description of occurrence.

2)

Identify the cause(s) for exceeding the limit (s) 3)

Explain corrective action (s) taken to mitigate occurrence.

4)

Define action (s) taken to prevent recurrence.

5)

Summary of consequence (s) of occurrence.

6)

Describe levels exceeding 40CFR190 in accordance with 10CFR20.405(c).

1 1.

Inoperable Containment Radiation Monitors, Specification 3.3.3.1.

j.

Steam Generator Tubing Surveillance -- Category C-3 Results, Specification 4.4.5.5.

k.

Maintenance of Spent Fuel Pool Structural Integrity, Specification 3.7.12.

i ARKANSAS - UNIT 2 6-19 Amendment No. 58, IJe91 1

L

.s ADMINISTRATIVE CONTROLS 1.

Radiological Environmental Monitoring Sample Analysis, Specification 3.12.1.

Unplanned Offsite Release during one hour period of 1) more than 1 m.

curie of radioactive material in liquid effluents 2) more than l

150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radiciodine in gaseous ef.fluents.

This report shall be submitted within 30 days of the occdrrence of the event and shall include the following information:

1.

Description of the occurrence.

2.

Identify the cause(s) of exceeding the limit (s).

3.

Explain corrective action (s) taken to mitigate occurrence.

4.

Define action (s) taken to prevent recurrence.

5.

Summary of the consequence (s) of occurrence.

SEMI-ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT" 6.9.3' Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operations shall be submitted within 60 days after January 1 and July 1 of each year.

• A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste system, the submittal shall specify the releases of radioactive material from each unit.

I I

i 4

ARKANSAS - UNIT 2 6-19a Amenoment No. 91 i

I i

ADMitilsTRATIVE C0ffTROLS 6.9.3.1 The radioactive effluent release report'shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste release from the unit. The data will be sumarized on a quarterly basis following the format.of kegulatory Guide 1.21. Revision 0, Appendix A.

6.g.3.2 Any changes in the DFFSITE DOSE CALCULATION MANUAL and PCP shall be included in the semiarnual report for the period in which the change (s) was made effective.

)

6.9.3.3 The radioactive effluent re. lease reports shall include the follow.

{

ing information for all unplanned releases to UNRESTRICTED AREAS of radio "

r i

active materials in gaseous and liquid affluents:

1.

Description of the occurrence.

2.

Identify the cause(s) for exceeding the limit (s).

3.

Explain corrective actions taken to mitigate occurrence.

4.

Define action (s) taken to prevent recurrence.

5.

Sumary of consequence (s) of occurrence.

5.9.3.4 The first report filed each year shall contain:

1.

A sumary of the hourly meteorological data collected over the previous calendar year. In lieu of including this suesnary in i

the report, the data may be retained by the licensee for NRC

• review and noted as such in the report.

2.

A summary of radiation doses due to radiological effluent during the previous calendar year calculated in accordance with the methodology specified in the OFFSITE DOSE CALCULATION MANUAL.

3.

The radiation dose to membert of the public due to their activities inside the site boundary. This calculated dose shall include only those dose contributions directly attributed to operation of the unit and shall be compared to the limits specified in 40 CFR 190.

6.9.3.5 The first report filed each year shall contain description of licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) during the previous calendar year.* *

• This information may be included in the annual FSAR update in lieu of i

inclusion in this report.

I ARKANSAS - UNIT 2 6-20 Amendment No. 60 s

i

~

1.

1

.o ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

• 6.9.4 Routine radiological environmental operating reports covering the operation of the unit during the previous caleodar year shall be submitted l

prior to May 1 of each year.

a.

The annual radiological environmental operating reports shall inclede sumaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activ-ities for the report period, including a comparison with preopera-tional studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2.

If hamful effects or evidence or irreversible damage are detected by the acnitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the prc,blem.

b.

The annual radiological environmental operating reports shall include sumarized and tabulated results of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

c.

The reports shall also include the following: a sumary descrip-tion of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from or,4 reactor; and the results of licensee partic-ipation in the Interlaboratory Comparison Program, required by

~

Specification 3.12.3.

'A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

ARKANSAS - UNIT 2 6-21 Amendment No. 60 4

s ADMINISTRATIVE CONTROLS' 6.10 RECORD RETENTION In addition-to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of unit operation covering time interval at each power level.

- b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items'of equipment related to nuclear safety.

c.

ALL REPORTABLE EVENTS.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specifica-tion 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operting License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfer and assembly burnup histories.

Records of radiation exposure for all individuals entering c.

radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient of operational cycles for those unit com-ponents identified in Table 5.7.1.

ARKANSAS - UNIT 2 6-22 Amendment No. 89 91

_ _ - _ - _ _