ML20203G320

Summary of 860605-06 Meetings W/Util,Southern Co Svcs, Westinghouse & Bechtel Re Instrumentation Tech Specs. Attendance List & Supporting Documentation Encl

ML20203G320
Person / Time
Site:	Vogtle
Issue date:	07/24/1986
From:	Mark Miller Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8608010073
Download: ML20203G320 (83)

Text

, _ _ - _ _ _ .

h Docket Nos.: 50-424/425 2 4 JUL 1936 APPLICANT: Georgia Power Company FACILITY: Vogtle, Units 1 and 2

SUMMARY

OF TECHNICAL SPECIFICATION INSTRUMENTATION MEETING HELD JUNE 5-6, 1986 The staff met with the applicant and its representatives on June 5-6, 1986, to discuss the instrumentation area of the Vogtle Technical Specifications (TS).

Participants are listed in Enclosure 1.

The staff and applicant discussed instrumentation including reactor trip system instrumentation, engineered safety feature actuation system instrumentation, remote shutdown instrumentation and accident monitoring instrumentation on June

5. Various radiological instrumentation TS were discussed on June 6.

Enclosure 2 contains the applicant's meeting notes transmitted by letter dated June 20, 1986. The applicant's notes also include its markups resulting from the meeting. The staff will review these suggested revisions during the TS review process. The staff incorporates these notes into the meeting suninary with the following additions.

Section 2.2.1, Table 2.2-1: The staff indicated that an appropriate note similar to that in the Catawba TS needs to be added regarding lead / lag compensation.

The applicant also indicated that the report of setpoint methodology for protection systems for Vogtle would be submitted for staff review in July 1986.

\S\

Melanie A. Miller, Project Manager .

PWR Project Directorate #4 l Division of PWR Licensing-A

Enclosures:

As stated I l

cc: See next page DISTRIBUTION: See Other Page P 3d WR-A El R-A PWR#4/DPWR-A P 1 r: h BJYoungblood 7/p /86 ~

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Enclosure 1 Participants NRC We stinghouse li Miller K. Daschke*

S. Brown R. Jansen*

F. Burrows * .

C. Willis**

Georgia Power Company Bechtel J. Swartzwelder 5. Cereghino J. Sutphin S. Mahler T. Wendt P. Kochery J. Hartka*

Southern Company Services J. Stringfellow Attended first day meeting only.

• • Attended second day meeting only.

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Enclosure 2 ATTACHMENT 1 .

i Notes from June 5-6, 1986 Meeting With NRC Staff on VEGP Unit 1 Technical Specifications

' s, .

I June 5, 1986 3.3.1, Table 3.3-1:

Concerning Functional Units 5 and 6, we proposed a relaxation of the Minimum i Channels Operable requirement during startup. The reviewer will have to give 1 our proposal further consideration. Concerning Functional Unit 6, Mode 3, we proposed a footnote which would allow blocking the Source Range High Flux at Shutdown alara in accordance with plant procedures. This is to allow startup without inadvertently actuating the alara. The reviewer will also have to give this further consideration.

Concerning Functional Units 14 and 15, our proposed Technical Specifications do not agree with FSAR Figures 7.2.1-1, Sheet 5 and 8.3.1-1, and SER Section j 7.2.1. We will have to resolve the discrepancy.

1 i We also explained that our proposed revision to Action Statement 5 is intended to address the situation where both channels of instrumentation are inoperable. The. reviewer will have to give this proposal further consideration.

A new footnote was applied to Functional Unit 12a which indicates that reactor trip on single loop loss of flow is active above P-8 only. A similar footnote was applied to Functional Unit 126 (reactor trip on loss of flow in two loops) which indicates that this trip is active above P-7 only.

See Att'a chment 2 for those revisions that were agreed to at the meeting.

3.3.1, Table 3.3-2:

The ICSB reviewer expressed concern that the response times shown in this table were not plant specific since many of the generic response times remain. We responded 'that our submittal was intended to be plant specific and that where the generic response times are called out,. these response times are indeed specific to the VEGP safety analysis.

4.3.1, Table 4.3-1:

With regard to the reactor trip bypass breakers, we reiterated our position that it is inappropriate for these breakers to be included in the Technical Specifications. However, we referenced certain material which was never made

available to the NRC staff. We have an action item to provide them with additional justification for this ites.

l

s -

The RSB reviewer will have to review our proposed revisions to Table Notations 3, 5 and 6.

See Attachment 2 for revisions which were incorporated at this meeting. I l 2.2.1, Table 2.2-1:

s The ICSB reviewer expressed concern s that our' submittal does not address all of the appropriate lead-lag time constants. We have an action ites to ensure that his concern is addressed.

See Attachment 2 for revisions which were incorporated at this meeting. 1 3.3.2, Table 3.3-3:

The reviewers could not accept our proposed incorporation of WCAP-10271, Supplement 2 in advance of the SER for Supplement 2. However, we tried to argue that the logic for doing away with STS Action Statement 15 and replacing it with Action Statement 20 is directly applicable from Supplement 1 of WCAP-10271.

The ICSB reviewer did agree to ' check with the reviewer responsible for the SER on Supplement 2 to WCAP-10271. '

]

1 The ICSB reviewer requested that we propose a note for the manual initiation I of Containment Ventilation Isolation (CVI) which refers back to the manual l initiation of Phase "A" Isolation and annual initiation of Containment Spray . j Concerning Functional Unit 6, the reviewer did not accept our proposed deletion of manual initiation of auxiliary feedwater. Our proposal is based on the fact that there is no sys*:aa level switch which will initiate auxiliary feedwater. Manual initiation is achieved by starting the pumps and manually modulating the valves to control flow. The reviewer suggested that we include

, the pump handswitches in the Technical Specifications. We have an action ites

to give this further consideration.

At this point, the ICSB reviewer stated that he felt that feedwater isolation on low Tavg coincident with reactor trip should appear in the ESFAS instrumentation tables. Our response to this statement was that no credit is taken for this function in the safety analysis. The reviewer suggested that we consider revising the PSAR to clearly state those functions that are not taken credit for in the safety analysis. We have an action item to investigate this question further.

Concerning Functional 6e, which is initiation of auxiliary feedwater (actor-driven pumps) on trip of both main feedwater pumps, we proposed a new Action Statement 25 which is less restrictive than that called for by the STS. The basis for our proposal was that this particular function is not taken credit for in the safety analysis. The reviewer will have to give our proposal further consideration.

1 i

See Attachment 2 for revisions incorporated during the meeting.

..wwa--y+- -%,.- w - . , - , - , - --r - - - . - , - - - - - - - - - - - . .-----s. , - - --- --,---.,r -w----y-, , - - - - - - - -m.c.

. -,_----,, g.--w - -

O 3.3.2, Table 3.3-4:

The reviewer asked about the methodology which will be used to arrive at the

! setpoints for the radiation monitors. We replied that the setpoints will have 1 an engineering basis but that the Westinghouse methodology would not be

applied.

s s

, 3.3.2, Table 3.3-5:

l This table is one of the items which was deleted from the Seabrook Technical l Specifications and placed in their FSAR. We have an action to give this 1

approach consideration.

This table was reformatted to be consistent with the way in which the response times were arrived at. That it is to say, the response time shown for each function is measured from the time that the init,iation signal is generated.

We also proposed deletion of the diesel generator response time on the basis that the time for generation of the safeguards signal is covered in this table whereas the actual start time of the diesel is covered in Section 3/4.8. The reviewer will have to give this further consideration.

! Concerning Table Notations 1, 2, 4 and 5, we had proposed adding the words

! "eignal sensing." However, with regard to notes 2 and 5, the question of whether this addition was appropriate was raised. We have an action item to check into this and to ensure that, where appropriate, the appropriate delays for signal sensing, diesel generator starting, and sequence loading delays are included in the response times.

The ICSB reviewer than brought up the ites in the SEE concerning the circuit modification necessary to prevent an undetectable failure in the testing I

circuitry,for the slave relays. He suggested that if we provide, in writing, a commitment that the appropriate circuit modification will be installed prior 1

to fuel load, this SER item would be satisfied.

1 3/4.3.3.5 The reviewer will have to give our proposed revisions to this specification further consideration. We will consider rewording our proposed Limiting Cor.dition for Operation to further define the required safety grade functions and support systems.

3/4.3.3.6 The reviewer will have to give our proposed specification further consideration. We have an ites to check into our commitments with regard to the Category 2 and 3 instrumentation.

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i - June 6 I l 3.3.3.1, Table 3.3-6 Concerning our proposed Action Statement 13, the reviewer suggested that we reword this action to require that if one means of auto-initiation of Containment Ventilation Isolation is inoperable, the other be operable.

s Otherwise the valves must be closed.. We havI an action to look into this.

See Attachment 2 for revisions incorporated during the meeting.

4.3.3.1, Table 4.3-3:

See Attachment 2 for revisions incorporated during the meeting.

3.3.1, Table 3.3-3: l i

The reviewer suggested that we need to redefine the operability requirements for instrumentation which initiates Containment Ventilation Isolation.

l the instrumentation (containment area low range radiation, and containment l ventilation gaseous, particulate and iodine activity) cannot be considered i equivalent. For instance, of the instrumentation listed above, there is no 1 back-up for iodine activity. We have an action ites to address this concern. l l 4.3.3.11, Table 4.3-9:

See Attachment 2 for revisions incorporated during the meeting. We agreed to

, use the wording found in the Catawba Technical Specifications for Table Notations 4 and 5.

l 3/4.11.1.4: '

r \

See Attachment 2 for revisions incorporated at the meeting.

3.12.1, Table 3.12-1: . -

i The reviewer requested additional justification for deletion of the l requirement to obtain samples of invertebrates from the Savannah River. We l have an action to provide this justification. '

See Attachment 2 for revisions incorporated at the meeting.

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1 ATTACHMENT 2 i

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TABLE 3.3-1 h REACTOR TRIP SYSTEM INSTRUMENTATION E

MININUM TOTAL NO. CHANNELS CHANNELS 'APPLICA8LE

,E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M00ES ACTION

-4

,e 1. Manual Reactor Trip 2 1 2 a 1 2 1 2 , ,5" 11

. . i

{,:5

. 2. Power Range, Neutron Flux d b

a. High Setpoint

b. Low Satpoint 4

4 2

2 3

3 1 2/

,2 2T 2&

b

3. Power Range, Neutron Flux 4 2 3 1, 2 2F High Positive Rate b

4. Power Range, Neutron Flux, 4 2 3 1, 2 ~, 2F High Negative Rate d

5. Intermediate Range, Neutron Flux 2- 1 2 Id2 3

6. Source Range, Neutron Flux c, ,

a. Startup 2 1 2 2F 4

b. Shutdown 2 1 2 3,4,5 5

7. Overtemperature AT a st 26 ff 2r Four Loop PI D ,

M,6 Four Loop Operation 4 2 3 .L. 2

8. Overpower AT _ T F T A d T r Loop Plant.

I b .

our Loop Operatio 4- L  :, 1, 2 #

a .

te =

p t

,.mr. -

-- .a-------- - - - - - - --.,----Eh -u +- - - ---

4 I e ll I

TABLE 3.3-1 (Continued) -

[

REACTOR TRIP SYSTEM INSTEMENTATION ,

r--

' MINIIRM E FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS CHANNELS TO TRIP CHANNELS OPERABLE APPLICABLE MODES ACTION I

3

e. 9. Pressurizer Pressure--Low 4 2 3 1

1. b

... l,

{

, 10. Pressurizer Pressure--High 4 2

• 3 . 1, 2 6b 5

11. Pressurizer Water Level--High # 3 2 2 I f 6h

12. Reactor Coolant Flow--Low

a. Single Loop (Above P-8) 3/ loop , 2/ loop in any oper-2/ loop in each oper .

I b b ating loop ating loop

b. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop If g below P-8) two oper- each oper-

• ating loops ating loop b 13. W 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2 ,

SteamGeneratokater Le~wel--Low-Low in any oper- each oper-ating sta. ating sta.

gen. gen. .

! 14. Undervoltage--Reactor Coolant p b Pumps 4-2/ bus ,2-1/ bus 3 1 6F

15. Underfrequency--Reactor Coolant p b Pumps 4-2/ bus 2-1/ bus 3 1 6P'

16. Turbine Trip 6

a. Low Fluid Oil Pressure 3' 2 2 1 6%

b. Turbine Stop Valve Closure 4 4 1. . I 12P

=

• 3 l ee i NSn also .)?uhau6M 3J 3.6 s

t

i .,

8

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L' b,

TABLE 3.3-1 (Continued) ,?

p' REACTOR TRIP SYSTEM INSTRtMENTATION MINIHLM TOTAI. NO. CHANNELS APPLICA8LE

]

FUNCTIONAL UNIT OF CHANNELS TO TRIP CHANNELS

. OPERA 8LE MDOES ACTION j if 3

s 17. Safety Injection Input y from ESF 2 1 2 1, 2 10 ,

4

' 9, . !C

. 18. Reactor Trip System Interlocks .

ti

a. Intermediate Range c. [

i Neutron Flux, P-6 4 2 1 2 27 8 [

L

b. Low Power Reactor Trips Block, P-7 ' -  !;~

P-10 Input 4 2 3 1 8  !?

or '

R P-13 Input 2 1 2 .

l' -

8 @

n Y c. Power Range Neutron [

• Flux, P-8 4 2 3 1 8 E

' V

d. Power Range Neutron 4 2 3 1 8 s.

Flux, P-9 h b

e. Power Range Neutron [

Flux, P-10 4 2 3 1,2 8 g,

f. Turbine Impulse Chamber k Pressure, P-13 2 1 2 1 8 $

k

19. Reactor Trip Breakers 2 10, 13 , l}.

c.

20. Automatic Trip and Interlock 2 1 2 1,= 2 a 10 h Logic 2 1 2 3**,4k58" 11 g q;

p

= . F

=  ;,

E I

t t

a ~. _ ..sy ..-E =:a h _ m 4 = m u aLalukuue m ke W c a:s , .

,=

TA8LE 3.3-1 (Ccntinued) .

TABLE NOTATIONS Q en the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

vetheP-7(LowPowerReactorTrip81oeg)setpoint.

O ove,the P-9 (Reactor Trip on Turbine Trip Interlock) setpoint.

b h provisions of Specification 3.0.4 are not applicable.

C, low the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

dM1ow the P-10 (l.ow Satpoint Power Range Neutron Flux Interlock) Setpoint.

$1 Table

. applicable Modes and Action Statament for these channels noted in 3.3-3 are more restrictive and therefore, applicable.

h Abse Me $-8(Si;rge. Loof l au offloW)St/pohf-ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel.

, to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - With the number of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. The Minimum Channels OPERA 8LE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 755 of RATED THERMAL POWER and the Power Range Neutron Flux Trip Satpoint is reduced to less than or equal to 855 of RATED THERMAL POWER iiithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2. .

e V0GTLE - UNIT 1 3/4 3-5 l T ,

APR S 4 %

! __ _ _- _ . __ - - .. _ . _L_._ -

. .: - ~ .----- u.---------

TA8LE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 - With the number of channels OPERABLE one less than the Minimum i

Channels OPERA 8LE requirement and with the THERMAL POWER level:

a. Below the P-6 (Intermedigte-Range Neutron Flux Interlock)

% Satpoint, restore the inoperable channel to OPERA 8LE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b .' Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 105 of RATED THERMAL POWER, restore the inoperable channel to OPERA 8LE status prior to increasing THERMAL POWER above IDE of RATED THERMAL POWER.

ACTION 4 - With the number of OPERA 8LE channels one less than the Minimum Channels 0PERA8LE requirement, suspend all operations involving positive reactivity changes.

ACTION 5 - With the number of OPERABLE channels one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel ,

to 0PERA8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor Trip i System breakers, suspend all operations involving positive reactivity changes and verify valves U08-U4-175, u08-U4-177,

, U08-U4-183, and U08-U4-178 are closed and secured in position within the next hour.

, ACTION 6 '- With the number of OPERA 8LE channels one less than the Total l

, Number of Channels, STARTUP and/or POWER OPERATION may proceed l provided the following conditions are satisfied: '

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 9

b. The Minimum Channels OPERABLE requirement is met; owever,

. the inoperable channel may be bypassed for up to @ hours j for surveillance testing of other channels per

Specification 4.3.1.1.

ACTION 7 - (Not used) l

ACTION 8 - With le'ss than the Minimus Number of Channels OPERABLE, within i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive i window (s) that the interlock is in its required state for the l existing plant condition, or apply Specification 3.0.3.

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V0GTLE - UNIT 1 3/4 3-6 g g4 g l

TA8LE 3.3-1 (Centinurd)

ACTION STATEMENTS (Continued)

ACTION 9 - (Not used)

ACTION 10 - With the number of OPERA 8LE channels one less than the Minimum s Channels OPERA 8LE reggirement, be in at least H0T STAN087 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERA 8LE.

ACTION 11 - With the number of OPERA 8LE channels one less than the Minimus Channels OPERABLE requirement, restore the inoperable channel to 0PERA8LE status within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />s-or open the Reactor Trip System breakers within the next hour.

1 ACTION 12 - With the number of OPERA 8LE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 13 - With one of the diverse trip features (undervoltage or shunt trip l

attachment) inoperable restore it to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and apply ACTION 10. The

-b'reaker shall not be bypassed while one of the diverse trip features

! is inoperable except for the time required for performing mainte '

nance to restore the breaker to OPERABLE status.

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l V0GTLE - UNIT. 1, 3/4 3-7 APR 84 #

I

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t

< i TABLE 4.3-1 b $

i;; REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS l c ,

TRIP ANALOG

• ACTUATING N00ES FOR [

CHANNEL DEVICE WHICH FUNCTIONAL UNIT CHANNEL CHANNEL OPERATIONAL

. OPERATIONAL ACTUATION SURVEILLANCE 'Ii CHECK CALIBRATION TEST' TEST LOGIC TEST IS REQUIRED i

1. Manual Reactor Trip N.A. N.A. N.A. R(14) N.A. 1, 2, 3 4 5

2. Power Range, Neutron Flu.v.

a. High Setpoint S D(2,4), Q(17) N.A. N.A. 1, 2 3 M(3,4),

Q(4,6),

R(4,5) cl

b. Low Setpoint S R(4) SU(1) N.A. N.A. 1*#, 2

?

!:' 3. Power Range, Neutron Flux, N.A. R(4) Q(17) N.A. N.A. 1, 2

• High Positive Rate T

g 4. Power Range, Neutron Flux, N.A. R(4) Q(17) N.A. N.A. 1, 2 High Negative Rate '

d

5. Intermediate Range, S R(4,5) S/U(1) N.A. N.A. 1T2 Neutron Flux

, 6. Source Range, Neutron Flux S. R(4,5, S/U(1),Q(9,17) N.A. N.A. 3, 4, 5

7. Overtemperature AT S Q(17) N.A. N.A. 1, 2 R(g)

8. Overpower AT S R Q(17) N.A. N.A. 1, 2

9. Pressurizer Pressure--Low .S R Q(17 N.A. N.A. 1 8

10. Pressurizer Pressure--High S R N.A. N.A.

Q(17[ 1, 2

11. Pressurizer Water Level-- S R Q(17) N.A. N.A. l' High

% 12. Reactor Coolant Flow--Low S R N.A. -

N.A. 1" Q(17)

7 TABLE 4.3-1 (Continued) fE REACTOR TRIP SYSTEN INSTRMENTATION SURVEILLANCE REQUIREENTS TRIP ANALOG ACTUATING M00ES FOR E CHANNEL DEVICE WHICH q CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE g FUNCTIONAL UNIT CNECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRE 0

13. Steam Generator Water Level-- S R Q(17,18) N.A.

N.A. 1, 2 Low-Low e

14. Undervoltage - Reactor Coolant N.A. R N.A. #QU9) N.A. l Pumps 8

15. Underfrequency - Reactor '

N.A. R N.A. mQ07) N.A. 1 Coolant Pumps 5:

8

16. Turbine Trip S/U,(1,10) N.A. N.A.

b

$ a. Low Fluid Oil Pressure N.A. R I Turbine Stop Valve N.A. S/U(1,10) N.A. Ib h b. N.A. R Closure

17. Safety Injection Input from N.A. N.A. N.A. R W. A. 1, 2

< ESF

18. Reactor Trip System Interlocks o a. Intermediate Range Neutron Flux, P-6 N.A. R(4) R N.A. N.A. 2 *c

_u , _ _ __ .__ __

F,.i f f i' T{ -a--_

._ g bg. Power Range Neutron ,

i Flux, P-8 N.A. R(4) R N.A. N.A. I C/. Power Range Neutron N.A. N.A.

Flux, P-9 N.A. 3(4) R I w '

A

e TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS

~

TRIP ANALOG ACTUATING MODES FOR E CHANNEL DEVICE WHICH 4 CHANNEL CHANNEL OPERATIONAL OPERATIONAL TEST ACTUATION LOGIC TEST SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED e

18. Reactor Trip System Interlocks (Continued) ,

e.' Power Range Neutron Flux,'P-10 N.A. R(4) R ,

N.A. N.A. 1, 2

f. Turbine Impulse Chamber

, .3 ,. Pressure P-13 N.A. R R N.A. N.A. 1

. @ a a .

1, 2, 3T 4T

[ ' ' 19. Reactor Trip Breaker Nfs.*tTb N.A. N.A. N(7. 11) N.A.

s 4 -

• 20 Automatic Trip and Interlock N.A. N.A. N.A. N.A. h(7) 1, 2, 3p 4T ,

T Logic .

4h

21. Reactor Trip 8ypass Breaker N.A. N.A. N.A. N(15),R(16) N.A. 1, 2, 3 a

e f1 t

.A 1

TABLE 4.3-1 (Continued) ,

OU TABLE NOTATIONS 0 Men the Reactor Trip System breakers are closed and the Control Rod Drive stem is gapable of red withdrawal.

9 '?(Ktw1&o on Twbe 7?/p ZdenosA/Se+foihf; s C., elow P-6 (Intermediate Range Neuty n Flux 1knterlock) Setpoint.

cl.dlow P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

Block e.(1)Son If not P-7 (Law /kerMaasr'Tydays.

performed in previous ,/s9;d (2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

• Adjust excore channel gains consistent with calorimetric ^

power if absolute difference is greater than 25. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 35. The provisions of Specification 4.0.4 are not, applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, and evaluated and compared to manufacturer's data. For the Intermediate Range and Power Range

. Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

~

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. ,

(7) Each train shall be tested at least every 62 days on a STAGGERED -

TEST BASIS.

(8) Not used (9) Quarterly surveillance in MODES 3*, 4*, and 58 shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive window. i Quarterly surveillance shall include verification of the Source Range High I

! Flux at Shutdown Alare Setpoint of less than or equal to 3.16 times background.

i

/ o i

N V0GTLI-UNIT 1- 3/4 3-13 APR 24 5

l

\ d <

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtMENTATION g . ~

NINI M '

5 TOTAL NO. CHANNELS CHANNELS APPLICABLE -

-4 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M00ES ACTION i w, -

1. Safety In.jection (Reactor J Trip, Feedwater Isolation, , i 1 Component Cooling Water, Control Room ii Emergency Mode Actuation, Start Diesel '

Generators, Containment cooling Fans,  ?

Nuclear Service Cooling Water, Contain- E ment Isolation, Containment Ventilation p Isolation,. and Auxiliary Feeduater f.

Motor-Driven Pumps).

a. Manual Initiation 2 1 2 1,2,3,4 ,e 19 f' n

, b. Automatic Actuation 2 1 2 1,2,3,4 14  !

a;s Logic and Actuation -

[-

y Relays d '

[

c. Containment Pressure--Nigh-1 ,

3 2 2 1,2,3 ISE '.

d. Pressurizer 4 2 .

3 1,2,3h 208  ?.

Pressure--Low f.

e. Steam Line Pressure-- 3/ steam line 2/ steam line 2/ stem line 1, 2, h 15 E

E Low ,

any steam line 1

fc.

I

$se ee r;

& 5l 7

f s g a aus, s ye m ea m 3.3.5 a>- Q 'l. _

r L'

i

. .l e

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Gi .

MINIMUM

$ TOTAL NO. CHANNELS CHANNELS APPLICA8LE ' '

-d FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M00ES ACTION , ,  !

2. Containment Spray , j

~

a. , Manual Initiation 2 1 with -2 ' 1, 2, 3, 4 19 2 coincident

, switches .

b. Automatic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation ,,

Relays

c. Contairement Pressure-- 4 2 3 1,2,3 -, 17 j y High-3* . 9

. e y' 3. Containment Isolation y

a. Phase "A" Isolation .

1) Manual Initiation 2 1 2 1,2,3,4 19 [

2) Automatic Actuation 2 1 2 1,2,3,4 14 [.

Logic and Actuation '

Di Relays gw; ggf -  ;'

3) Safety Injection See b l. above for all Safety Injection initiating functions and requirements. U

4) Containment Area Radiat-on (High Range 2 1 2 1,2,3,4 N f g

i E-owS, RE , t'l f b

{

L Q $$9 Cif$$$M *3* b . '

k 1

o TA8LE'3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUENTATION -

h E

MINIMUM

. E TOTAL N0. CHANNELS CHANNELS APPLICA8LE .

Q FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION M

b. Containment Ventilation i

~l

' Isolation ' '

1) Manual Initiation 2 1 2 1,2,3,4,6 0 18,14

2) Automatic Actuation 2 1 2 1,2,3,4,6" 18,14 ,

Logic and Actuation Relays

pe+Ia,nI %tif .

3) Safety Injection See 14em 1. above for all Safety Injection initiating functions and 4:' requirements. f i

• ) Contalmeent Area l 'i' Radiation (Low Range)* 2 1 2 1,2,3,4,6" 18, %

t;; (g . . q A 1)*Eontainment Ventilation ,

Radiaton

1) Particulate (A&M)1 1 51 1,2,3,4,ff 18, %

11) Iodine (RE-ZS58) 1 1 si 1,2,3,4,6C 18, &

111) Gaseous (ftE-6GE) 1 1 51 1,2,3,4,6" '18,16

. 4. Steam Line Isolation ,

,' a. Manual Initiation

1) Individual 2/ steam line 1/ steam line 1/ operating - 1,2f3E 24 steam Ifne c i 2) System 2 1 2 1, 2 Y 23 .

b. Automatic Actuation 2 1 2 1, 2 3 22 5, ' a'c ad ac' a Relays e.

4 ,u, sp.a n a .n 3 s. u . M l .

l

?

E

. TABLE 3.3-3 (Continued) .

(

k ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION f I;;  ::

h MININUM [

3 FUNCTIONAL UNIT TOTAL NO. CHANNELS CHANNELS APPLICABLE .

-4 OF CHANNELS TO TRIP OPERABLE _ MODES ACTION

{

s y 4. Steam Line Isolation (Continued) y J v

c. ' Cuntainment Pressure-- 3 2 2 1, 2, 3' 15

• Htigh-2 4g g ,

d. Steam Line Pressure--Low 8 3/ steam 2/ steam 2/ steam 1, 2, 3 O 15 " I line line any line $

steam line  ;

i

e. Steam Line Pressure - bf d <

w Negative Rate--High 3/ steam 2/ steam 2/ steam 3^^^ " /~ 15F ,

line line any line j 5 steam line j

T 5. Turbine Trip and -

Feedwat.er Isolation

(

E5 , i

a. Automatic Actuation 2 1 2 1, 2 25 i Lcgic and Actuation Relays -

f

b. Steam Generator 4/sta.. gen. 2/sta. gen. 3/sta. gen. 1, 2 20 r Water Level-- in any oper- in each [

High-High (P-14) ating sta. operating  ;

gen. sta. gen. s

c. Safety Injection See Item 1 above for all Safety Injection initiating functions and b requirements.

6. Auxiliary Feedwater f

[.

a. Manual Initiation 2 1 2 1,2,3 23 y 6- ^ata atic actaatiaa 'aaic 2 222 5p and Actuation Relays .

2 2 22 4

.F.

• c. ' r Sta. Gen. Water Level-- i-Low-Low # '

&See also $feciffral ion .L3. Sob

. t,

. g

]

e TA8LE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION MINIMtm TOTAL NO. CHANNELS CHANNELS APPLICA8LE

, E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE MODES ACTION .

1 G

6. Auxiliary Feedwater (Continued)

!, s 1) . Start Motor- d [

. Driven Pumps 4/sta. gen. 2/sta. gen. 3/sta. gen.. 1,2,3 20# 'o '

l *

. in any oper- in each ating sta. gen. operating sta. gen.

I 2) Start Turbine- d i Driven Pump 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2, 3 20 "

s in any in each 2 operating nperating i sta. gen. sta. gen. j I w d. Safety Injection l 5 Start Motor-Driven Pumps See Ites 1. above for all Safety I\ njection initiating functions and w requirements.

O 1 A e e. Loss-of .L .4W fI("M f.sf Bus a/f7<.

t i Start Motor-Driven 4/ train 2/ train 3/ train 1, 2, 3, 19 Pumps 11 Turbine-Driven Pump 4/ train 2/from 3/ train 1, 2, 3, . 19

. either train l, f. Trip of All Main '

Feedwater Pumps,

Start Motor-l Driven Pumps and Edxitz.- . 2 1 1 1, 2 19

,..mm ,____. . - , , ,o -

____..m t_

a- a--- -

7. Semi-Automatic Switchover to l

5, Containment Emergency Sump .

I

• a. Automatic Actuation 2 1 2 1,2,3,4 14 ,

Logic and Actuation Relays .

,g p

e

1. 5' h

TABLE 3.3-3 (Continued) b t

< r.

k ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION a MINIMUM $

F c TOTAL NO. CHANNELS CHANNELS APPLICABLE ,

3 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION  ?.

H 7. Semi-Automatic Switchover to '

4 Containment Emergency Sump (Continued) , ,

b. RWST Level--Low-Low 4 (wAm4Mf2 3 1,2,3,4 17 i Coincident with Safety See Meer 1. above for all Safety Injection initiating functions i Injection and requirements. f E

/ Coincident Wilhi -

_f Containment Sump Level--High 4 2 3 1,2,3,4 17 R Pand . f

( Safety injection See It'en 1. above for all Safety Injection initiating functions and iequirements. f

8. Loss of Power.fo YlsNVW Eus d U EsF >

m a. 4.16 kV Emmegemey Bus 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 ' 20

• 2,3 g undervoltagossofVoltage af b. 4.16 kV Emeegemey Bus  ;. .

N

" Ucdervoltage-Grid Degraded cl -

Voltage 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 20F ~

e.

9. Engineered Safety Features E Actuation System Interlocks , 7

a. Pressurizer Pressure, 3 2 2 1,2,3 21 5-P-11 l

. b. Reactor Trip, P-4 2 1 2 1,2,3 23 i

10. Control Room Emergency Mode I Actuation L2 8 e en,3,4,5 , (o j , f

a. Manual Initiation 2 1 1 26 l

'"a

6- ^"' ^" " $2 5ee and Actuation Relays 2 1 1 M ,#> 5e ">26 '

a s

• y 3 4, Sa lo .

i a

c. taggRagogggnitor 2 g.p l 1 2

[9

{ d. afetyinjection' See Men 1 above for all Safety Injection initiating functions '

and requirements. 4 r

b

'l

7- .

TABLE 3.3-3 (Continued)

TABLE NOTATIONS cl.dheprovisionsofSpecification3.0.4arenotapplicable.

• *'ry ', .c.;ir ; _ _ _ L;id ' - th ' "^^' h .i t h "- r _ n _ _ _ Tang -

,..__._a ,_ __-

~

Av55ai C.wDuehi+ confelnm enf. itradWed hI o/mveMost a f kuds ouw b.***%ip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

S.

Q.4frip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.-

b ACTION STATEMENTS dCTION14-WiththenumberofOPERABLEchannelsonelessthantheMinimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1, provided ,

the other channel is OPERABLE.

ACTION 15 - With the number of OPERA 8LE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

/2tpleee ea R.7Mw+ p-! yjyy zy 7w mn .w =>Ui . w.nnel associated with an operating loop inope'rable, f

restore the inoperable channel to OPERA 8LE status.within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. One p channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 3 ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable

, channel is placed in the bypassed condition and the Minimum Channels OPERA 8LE requirement is set. One additional channel may be bypassed for up to 2~ hours for surveillance testing per Specification 4.3.2.1.

t ACTION 18 - With less than the Minimum Channels OPERA 8LE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

e .Duav movement af itradWod rued or mwemenf W / ads ove-N iWdidef kl.

C No+ appitutsk if ou main sham hola% talve om'assninfel byau

}solafiM V4NLjur Skarn/ int lJ c/rt&

l V0GTLE - UNIT-1 3/4 3-23 APR 14 w-9

Insert to page 3/4 3-29 C'..: 23 ACTION 16 - With the number of OPERABLE channels less than the Minimum _

Channels OPERABLE requirement, comply with the ACTION

% requirements of Spec 4,fication'3.9.9'(Mode 6).

1 0

)

i

.i e

h

n. . .. .. ._...-aE M u ~ , M " Ei ~ & *- 4 w = nk E W i

., AYI.

l.. .

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 19 - With the number of OPERA 8LE channels one less than the Minimum 1 Channels OPERABLE requirement, restore the inoperable channel l to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANOBY l s within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />st,and in.C8LD SHUTDOWN within the following j 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. -

l l

ACTION 20 - With the number of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following ccnditions are satisfied:

a. 'The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and

b. The Minimum Channels 0PERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for sorveillance testing of other channels per Specification 4.3.2.1.

/4wurbe, af d/kt.4st.2 cAennk It ACTION 21 - WithAless than the Minimum 40mmbusmg6-Channels within OPER 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of'the associated permissive.5fe/Wr

[kfff' state

---

for

' ^rthe tc._ 'l that the interlock is in its required existing plant condition, or apply Specification 3.0.3.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERA 8LE requirement, be in at least H0T STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least NOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

@ Ti ACTION 23 - With the number of ERA 8LE channels one less than the 8eest-Mi#/**1 '

Numbe m 6 Channels restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T STANOBY within i

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following

, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

i

ACTION 24 - With the number of OPERA 8LE channels one less than the Total

Number of Channels, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the ACTION required by Specification [3.7.1.5].

ACTION 25 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERA 8LE requirement, be in at least NOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERA 8LE.

j SSE .Tuen kr py .,1lY J-2 f

V0GTLE - UNIT 1 3/4 3-24 l .

m w.-

1. 0

Thskt~ S f*)4 I/Y$~ZY

ACTION W - With the number of OPERABLE channels one less than the.

& total number of channels, restore the inoperable channel to OPERABLE. status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the Emergency mode. With two channels inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the Emer-gency mode.

ACTION 5 - With the number of channels OPERABLE one less than the Mini = = Channels OPERABLE requirement, restore the number i

27 of OPERABLE channels to the Minimum Channel OPERABLE require-ment within 7. days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t l

, *C 6

I e

l l

{

k TABLE 3.3-4 (Continued) '

~

1 ENGINEEREO SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS E

' SENSOR TOTAL ERROR E FUNCTIONAL UNIT ALLOWANCE (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE w ,

e4 3. ContainmentIsolation; ,', , l ,, , , , l ,

a. Phaie'"A" Isolati' o n ' '

1) Manual Initiation N.A. N.A. N.A. N.A. N.A.

2) Automatic Actuation Logic N.A. N.A. N.A. H.A. N.A.

and Actuation Relays

. ~

, ., ,n. 3) Safety Injection , Item 1. above for all Safety Injection Trip Setpoints and

,j? lowable Values.

4) '

{ ContainmentAreaRadiation)(N.A.)

(High Range)(AE-0005 tham (N.A.) (N.A.) (N.A.) (N.A.) ~;

Y b. Containment Ventilation -

E Isolation a

1) Manual Initiatton N.A. N.A. N.A. N.A. N.A.

2) Automatic Actuation N.A. N.A. N.A. N.A. N.A.

Logic and Actuation [lr.

, Relays i-

3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and  :,'

. Allowable Values. d

. E

.4) Containment Area Later Later Later Later -

Radioactivity (Low  ::

)-" Range) (AE-oAs2, Af-W.7)  !!

s

5) Containment Ventilation b Radiation ($t~2Sc.%) [i.

1 Particulate Activity Later Later Later

• 11 Iodine Activity (AE-25658)Later Later Later Later Later 111 Gaseous Activity (#615W8)Later Later Later Later

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS E I

' SENSOR i TOTAL ERROR E FUNCTIONAL UNIT ALLOWANCE (TA) Z_ (S) TRIP SET' POINT ALLOWA8LE VALUE

-i w 4. Steam Line Isolation i i

a. Manual Initiation N.A. N.A. N.A. N.A. N.A. }'

i- b.' Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

and Actuatiori Relays

c. Containment Pressure--High-2 3.0 0.71 1.5 115.0 psi;; $15.8 psig ,

{ d. Steam Line Pressure--Low 13.1 [10.71] [1.5] 1585 psig 1567 psig"

e. Steam Line Pressure - 5.0 0.5 0 -<100 psi /s -#123 psi /s** i y Negative Rate--High y 5. Turbine Trip and Feedwater >

l y Isolation '

j a $

a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. C

Actuation Relays 1 *

b. Steam Generator Water '5'.1 2.18 1.5 <78.0% of <79.8% of narrow Level--Nigh-High (P-14) harrow range range instrument instrument span. -

kikr.)%it j c. Safety. Injection See Men 1 above for all Safety Injection Trip Setpoints and Allowable Values. .

A

6. Auxiliary Feedwater

a. Manual Initiation N.A. N.A. N.A. N.A. N.A. k

• t

b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. '

/

h and Actuation Relays r h

, . '. (

e 0 e.

TABLE 3.3-4 (Continued) f.

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS X, -

fl SENSOR TOTAL ERROR ,l y FUNCTIONAL UNIT ALLOWANCE (TA) Z (5) TRIP SETPOINT ALLOWA8LE VALUE r

-i l  :!

s 6. Auxiliary Fee &#ater (Continued)

)l.

c.

Steam Generator Water Level--Low-Low

. I j$

b

1. Start Motor-Driven 17.0 12.18 1.5 >17.0E of >15.3% of ff Pumps r. arrow range narrow range r' instrument instrument span. p, i span.  ?

2. Start Turbine- 17.0 12.18 1.5 >17.0E of >15.3% of .,

Driven Pump Earrow range Warrow range w

instrument span.

/ instrument span.

(

k

functiaul H^i'l~ '

V1 w d. Safety Injection See 14ee 1. above for all Safety Injection Trip Setpoints and i.i d Start Motor-Driven Pumps Allowable Values.

9 k

e. Loss-oforde ^":.fsfedy./G

-74 kVEsf Bn 6/Aje- F

'j i Start Motor-Driven Pumps N.A. N.A. N.A. 3598 volts with >3548 volts with ,.l 20 s time delay 5,20 s time delay R 11 Turbine Driven Pump N.A. N.A. N.A. 3598 volts with >3548 volts with .-l Trip of All Main Feedwater N.A. N.A.

20 s time delay 720 s time delay ['

f. N.A. N.A. N.A. P Pumps, Start Motor-Driven Pumps and Turbine-Driven '

Pump -

[jr

. Suction Transfer on Low N.A. N.A. N.A. -< [442] ft -< [441] ft .l 5 eressure

90 $:

s>=

• i y .

[-

e

i

.h l TABLE 3.3-4 (Continued) 8 '

,l

$ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS i g , i

, . SENSOR c TOTAL ERROR z FUNCTIONAL UNIT ALLOWANCE (TA) Z (S) TRIP SETPOINT All0WA8LE VALUE

-e w 7. Semi-Automatic Switchover to i *

Containment Emergency Sump .

I

a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. -

and Actuation Relays -

I i b. RWST Level--Low-Low N.A. N.A. N.A. 274 in. from 254 in. from tank base3f

! Coincident With tank base 35.6% 32.5% of instrument af initrument span span [

Containment Sump Level N.A. N.A. N.A. 5 D0] in. *$ [32.5] in. i and Fo=#sonal 41f-above [680] ft above [680) ft  !

afety Injection See bl. above for all Safety Injection Trip Setpoints and w Allowable Values.

8. Loss of Fower l0 Ylk }W SSF S'U Y BSP E a. 4.16 kV f :..:-:,- Bus N.A. N.A. N.A. 2912 volts , >2912 volts l Undervoltage-Loss of Voltage with a with a < 0.8 i

< 0.8 second time iecond time delay. ['

delay. [.

2SF t

- b. 4.16 4 kV L . ,_.._, Gus N.A. N.A. N.A. 3598 volts 3598 volts  :

Undervoltage-Grid Degraded with a 20 with a 20  ;

I Voltage second time second time L-delay. delay. 9

9. Engineered Safety Features

• Actuation System Interlocks i ao a. Pressurizer Pressure, P-11 N.A. N.A. N.A.

• 5 1970 psig 5 1981 psig n

[.

g b. Reactor Trip, P-4 N.A. N.A. N.A. N.A. N.A. ,

f

. . k.

. y,,

6 s .

TA8LE 3.3-4 (Continued) 1

?

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETP0INTS ,,

$ 4:

b '

SENSOR

• TOTAL ERROR (S) TRIP SETPOINT ALLOWA8LE VALUE -

E FUNCTIONAL UNIT ALLOWANCE (TA) Z_

Y .-

,. p 10. Control Room Emergency Mode ,

Acthet M 1

fjc/s*4fIk1- -( E;

a. Manual Initiation N.A. N.A. N.A. N. A. - N.A.

b. Automatic Actuation I Logic and Actuation Relays N.A. N.A. N. A.' N.A. N.A.

kcfloou/Zfr/f -

{

c. Safety Injection See .Mee-1 above for all Safety Injection Trip Setpoints and Allowable Values, y.

O P

Intake Radiogas monitor (N.A.) . (N.A.) (N.A.) (N.A.) '(N.A.)

R d.

(BE-1211(a, /C- 12/17) f s

• b.

B

• b i

c.

b-.

).

e r

L

&G%b _

u .: ui.3 .. . 4-dh;e% W '-ML % .Y.: a Nu: a..~:n .Oa a.: . . :u I

~

TABLE 3.3-5 .

ENGINEERED SAFETY FEATURES RESPONSE TIMES I

INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS l l

1. Manual Initiation

. l

' a. m Safety Injection (ECCS) s -

N.A.  !

b. ' Containment Spray N.A. l

c. Phase "A" Isolation N.A.

d. Auxiliary Feedwater Motor-Driven Pumps N.A.

A "--':' _ . ,  ;... ...._M__' I- ' d ;;- -- ""

l C r. Steam Line Isolation N.A.

" :i::';- '::!:"::

m_.__ .. . '

.,_., _ _ ...m.

, ,__..,____.u_m>, _ ,__ ,__,_ ,__ ..

< e__ _ ____. . . ,__ __

.c

,. _ _ . _ _ . _ _ _ _ _ _ _ . _ . ...m. . i (f. N.A.  ;

ControlRoomgrggcyModeActuation

$4 Reactor Trip N.A.

hg. Start Diesel Generators N.A. I 1 C-- :.:.^ "- - " '-- .',. "..- l

.__ _>____, e..,,__ __.

. ^ ... ^ _ . . ' ;; ih ' ; ";^ _ . .

l1. Containment Pressure--High-1

a. Safety Injection (ECCS) i 2951)/12(5)

b. # Reactor Trip (from SI) i2 C. Jf' dwater A', Isolation < 7(3) d, # - Ase. '----

Isolation < 2(6)

c. 47 Containment Ventilation Isolation 1 6.5 E # Auxiliary Feedwater Motgr-Drivy Pumps 1 60

$. W Nuclear Service (ooTing d (e5 1 100(1)/86(2)

h. 8 Containment Cool g Fans < 40(1)/28(2)

I g Control Roo b rge h b Actuation N.A.

y 4 Start Diesel Generators 1 (10]

Sm/mfr .TsolWMrs N,4 I

% a,erf Gok 6%fw N,A, i  % h/yn d /44 fw Nid.

Nuled rew,u CeG f+~ N.4 Carfoo'rorerfs yktVer/&/n khAM Al1 y.,4.

V0GTLE - UNIT 1 3/4 3-32 gygg4jg,

- a ma - :: _ - c . mwv ~-- m ; -- - a- = . a. .a .xa a; ; .:. . .;;..QL

- - ~ ~ . -.

.~...._Y'

• TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING $1GNAL AND FUNCTION RESPONSE TIME IN SECONOS

3. Pressurizer Pressure.-Low

a. 5 ety Injection (ECCS) 1 29(1)/12(5)

' b- Reactor Trip (from 5 0 <2

c. M F at

' pr, Isolation 7(3) cl. Jf : --

Isolation 2(6) 8 M Containment Ventilation Isolation [6.5

f. M Auxi,11ary Feedwater OrgnPumps 1 60 -

9. _ff Nuclear Service d ter < 100(1)/86(2)

h. .g Containment Coolyi Fans 'I40(1)/28(2)

j. M Control Room d rge h h Actuation N. A. '

S. [ Start Diesel Generators 1 (10]

10) 0 7 :......

^

.., _ _ . ]

4. Steam Line Pressure--Low

a. Safety Injection (ECCS) < 12(5)/24(4) b M Reactor Trip (from SI) 2 d- MF 7(3) '

39 Mgdwater Isolation

d. Isolation I2(6)

e. M Containment Ventilation Isolation [6.5 6 .5/ Auxiliary Feedwatef r-Driven Pumps < 60

3. .kf Nuclear Service kool ng Tte k 100(1)/86(2)

h. g Containment Cooling Fans 1 40 III/28(2)

j. 8 Control Roon IEm[vT k 5 de Actuation N.A.

d. 8 Start Diesel Generators 1 (10]

1^' "- ;::::t "n" ; _. 2

-7

b. Steam Line Isolation 3) 1[

5. Containment Pressure--High-3

a. Containment Spray ,

1 88(2)/100(1) l

6. Containment Pressure--High-2 '

Steam Line I, solation 3)

, s i 7. Steam Line Pressure - Negative Rate--High Steam Line Isolation < 7(3)

~

V0GTLE - UNIT 1 3/4 3-33 g 34 w, t

- - - . . . . _ . . . - - - - - - - - - _ . -.~. .

---.__---...L---.---.,,..---.-.._, -w

.sn%Cw%L.;-.c.n ., -:185Musik. L?%% e L.n.- - -

a u~a wefm.is .

TABLE 3.3-5 (Continued) .

ENGINEERED SAFETY FEATURES RESPONSE TIMES l l

_ . _ _ INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS

~

8. Steam Generator Water Level--High-High

a. Turbine Trip '- -

< 2.5

b. Feedwater Isolation f7(3)

9. Steam Generator Water Level--Low-Low l

a. Motor-Driven Auxiliary i Feedwater, Pumps < 60 '

b. Turbine-Oriven Auxiliary i Feedwater Pump < 60

10. Loss-of-Auxiliary Feedwater s 60 l

11. Trip of All Main Feedwater Pumps j

1. Motor Driven Pumps M.A.

_..._ , 2.- Tut' : ac'---- -

=*--

12. RWST Level--Low-Low (o/gc/k/ /4///r S/e/y 5/schuf j e_ f ' :'j:..^. . : ^... :_ . ., :..;;;;u e.. -Nehr-

b. oincident witn containment S W evel--High and Safetv'Intaction -

ami automatic Switchover to Containment .

Emergency Sump 146(2)/60(1)

13. Loss of Power E.s F .y

a. 4.16 kV Essaymoy Bus Undervoltage- 1 2.0

• !'s N*

4.16 kV* "-;:

h?/:yhBus Ar*.re/ Gageafe LR

b. 1 21.2 Undervoltage - Grid Degraded Voltage

i. ShwYakyna/)r dirle/ SewsAre

14. Control Room Intake Radiogas -

~

Control Roon Ventilation Emergency Mode Actuation i 10.0 (Isolation)

15. Containment Radioactivity

a. Area Radiation Low Range-Containment Ventilation Isolation i 15.0

b. Containment Ventilation Radiation-Containment Ventilation Isolation i 15.0

c. Area Radiation High Range-Containment Isolation Phase A i 15.0 V0GTLE - UNIT l' 3/4 3-34 g 34 g )

.- . . - _ ~ . ~ - wy. , . . . - - -

l m x u . . .,.w .w.a a:. ..a l TA8LE 3.3-5 (Continued) .

TABLE NOTATIONS

?/ **fS/gj (1) A@ Diesel generator j stading and sequence loading delays in (2) Diesel generator starting and sequenge loading delay M included.

S Offsite power available. s.

Electrohydraulic valves.

(3) fgreal Sersig, (4) AlHesel generator starting and j sequence loading delay included. RHR pumps not included.

i l

(5) Diesel geherator starting and sequence loading delays not included.

RHR pumps g included. ,

.(6) Does not include valve closure time.  :

1 1

j 8 g he ($$ r13 2 & t, S W //f C /V k l k l h / At t $ QS$6 Cf'fl wi+4 W ktc d to/4 s9 rely a.s cWeenkm/ m; 7]De .7,.14 pAu **1: 4 a d' if/ w / A 2 R/ seceds onockhd w/M uferpe/g mra/ ck cpH eyenfik.

• *7;4e msa +,u,<. sw/ inclua'e Ak h,,e di onoeget aliM xarden'*//ny rey a.i defermined Ti b /r r. 3 4 plas m wa'd/Mno/ /,2 .secodt ossoce;4d wi/4 iderforig re/ as n / c /r' ' '/ / 'f dr*ffon.

O I

e V0GTLE - UNIT 1 3/4 3-35 l

APR 14 W i

i

Ye j

s .

(

l l

TABLE 4.3-2 i 4

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION 4-g SURVEILLANCE REQUIRENENTS k TRIP f '

E ANALOG ACTUATING N00ES '

4 CHANNEL DEVICE ' MASTER SLAVE FOR WHICH

,e CHANNEL . CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

! P FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED i D l o '- ' .

1. Safety. Injection (Reactor Trip, -

) Fee hater Isolation, Component  ;,.

! Cooling Water, Control Room .

i Emergency Mode Actuation, Start !l

! Diesel Generators, Containment Cooling Fans, and Nuclear Service Cooling 4 Water, Containment Isolation, t Containment Ventilation Isolation, and h tl' Auxiliary Foe hater Motor-driven Punps). -j N s.

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 [

l h b. Automatic Actuation N.A. N.A. -

N.A. If.* A. M(1) M(1) Q 1,2,3,4 5 j Logic and Actuation . .

f.

Relays a

(

c. Containment Pressure- S R M N.A. N.A. N.A. N.A. 1, 2, 3 Nigh-1 l

'd. Pressurizer Pressure Low S R M N.A. N.A. N.A. N.A. 1, 2, 3

(

e. Steam Line S R M N.A. N.A. N.A. N.A. 1, 2, 3 I

Pressure-Low g )

c

2. Containment Spray -

. a. Manual Inttiation N.A. N.A. N.A. R N.~ A. N.A. N.A. 1, 2.*3, 4 [

b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 I g Logic and Actuation

! A Relays  ;

• • N.A. 1, 2,-

S R M N.A. N.A. N.A.

. c.ContaigntPressure-High-3

[k tl.

t Set also Sf ce*[thnv/Ild Y 3 3 6.

5

. F

. 4

?

TABLE 4.3-2 (Continued) g

.c .,

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRt#tENTATION

{

SURVEILLANCE REQUIRENENTS E (

TRIP ,y E ANALOG ACTUATING MODES q CHANNEL DEVICE MASTER SLAVE FORtetICH.p g CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLAN i t, FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST ISREQUIRE&j.

3. Containment Isolation - .

h t

a. Phase "A" Isolation

(.

1) Manual Initiation M.A. N.A. N.A. R N.A. N.A. N.A 1, 2, 3, 4 f.

2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1,2,3,4'

, Logic and Actuation - sj R

3) Safety Injection

& c//pg N W ,

See-1&am 1. above for all Safety Injection Survalliance Requirements.

f

[ .

[

4) Containment Area Radiation e) S R M N.A. N.A. N.' A. N.A. 1, 2, 3, 4 I

((Ninh Rang /E-MeC)

/f-De6, i

b. Containment Ventilation Isolation e

[

5-i

1) Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 E

.. 2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 p Logic and Actuation  ;

Relays ,

g .g .p i 3) Safety Injection See-Stem 1. above for all Safety Injection Survel11ance Requirements. i

! 4) Containment Area gadiation (Low Range) S R M N.A N.A 'N.A N.A l Q (AE-ooo2, /E- 6del} 1,2,3,4,l R .-

= F

) E ,

I

- [j -

.i M-

%j 4' F

. t

' # F..

y TABLE 4.3-2 (Continued) [j EllGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRIS H TATION SURVEILLiuuLt REQUIRDENT5 f g .

, i, TRIP rj g ANALOG ACTUATING ,

M00ES y

" CNANNEL DEVICE MASTER SLAVE FOR WICN CNAISIEL - CNANNEL CNAISIEL OPERATIONAL OPERATIONAL ACTUATION i'.

" RELAY RELAY SURVEILLANCE 1 F W CTIONAL'tallT '

CHECK CALIRRATI0ll TEST TEST LOGIC TEST TEST TEST IS REQUIRED

)l Containment Isolatten (continued) it- t i~ r, .i' - .a . i .. i . . ' - it' f

' r 1 5) Containment Ventilation . '

b1 Radiation 4

1 Particula Activity R M N.A. N.A. N.A. N.A. 1,2,3,4,6

[

j 11 Iodine g

{

u 1

Activittt-W58)S R M N.A. N.A. N.A. N.A. 1,2,3,4,6 N

)

1 g

lli Gaseous ((#E-2535'b

4. Steam Line Iselation Activity R ,M N.A.. N.A. N. A. ,

N.A. 1,2,3,4,6 L.

l , rj

! [ a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. ii. A. 1, 2, 3 l

h b. Automatic Actuation Logic.and Actuation N.A. N.A N.A N.A. M(1) M(1)-

Q 1, 2, 3 h p

j Relays 4

c. Contalapent Pressure- S R M N.A. N.A. N.A. N.A. 1, 2, 3 0 Nigh-2 8 , ,,

I/;

) d. Steam Line S R M N.A. N.A. N.A. N.A. 1, 2, 3 h j Pressure-Lou -

e. Steam Line Pressure- S R H N.A. N.A. N.A. N.A. 3 Negative Rate-Migh y

5. Turbine Trip and Feedsater r

} Isolation - '

(.

) a. Automatic Actuation N.A.

N.A. N.A. N.A. M(1) M(1) Q 1, 2 l g Logic and Actuation i-I 33 Relays 7 b. Steam Generater Water Level-Nigh-Nigh (P-14) 5 R N.A N.A. N.A. N.A. N.A. 1, 2 y p g

I- c. Safety Injection See Item 1 above for all Safety Injection Surveillance Reouirements. -l' j i g Sowe//jance fqq'gmQ, oncident Containment R M N.A. N.A. N.A. N.A.

with Sump Level-High i 1 and  ?

$ Safety Infection See Ites 1. above for all Safety Injection Surveillance Requirements.

i Y 8. Loss of Power /a E/4M & ils 8 ssf l a. 4.16 kV Busegamey N.A. R N.A. M N.A. N.A. N.A. 1, 2, 3, 4

Bus Undervoltage-Loss

of Voltage J EJrp l b. 4.16 kV W N.A. R. ~. N.A. M N.A. N.A. N.A. 1, 2, 3, 4 -

j - Bus Undervoltage-Grid i Degraded Voltage l 9. Engineered Safety i

l Features Actuation System Interlocks Wy '

L N

5, a- rr rir r a a- a a a a- # a- # a- a.a. 1, 2. 3

-l Pressure, P-11 '

b. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3, I

! l i

(

e TA8LE 4.3-2 (Continued) i  ;

j h ENGINEERE0 SAFETY FEATURES ACTUATION SYSTEN INSTRWENTATION i g SURVEILLANCE REQUIREE NTS -

'j TRIP h E

y ANALOG ACTUATING DEVICE MODES j CHANNEL MASTER SLAVE FOR WICN i w CHAWEL CHANNEL CHAMEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANC l FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRE 07

10. Control Roos Ventilation Emergency Mode Actuation

}[c m

a. Manual Initiation M.A. N.A. N.A. R N.A. N.A. N.A. All Modes f C

b. Automatic Actuation 7 i Logic and Actuation '

Relays N.A. N.A. N.A. N.A. M(1) N.A. N.A. All Modes i i u *b 1 c. Intake Radiogas  ?

• w Monit r S R M N.A. N.A. N.A. N.A. All Modes a W 'g"b M*"y") FauMauf tinif g

" d. Safety Injection See .Mue1 above for all Safety Injection Survalliance Requirements .

TABLE NOTATION . II t

! (1) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS. b g.

i 1 L R

. In

p V,

l.

A '

{:

I

[ l

• l i

=

M ' ['

I

q h

4 ,

l>

TABLE 3.3-6 ,!

RADIATION MONITORING INSTEMENTATION FOR PLANT OPERATIONS

! E I

• ~

. MININUN i E CHANNELS CHANNELS APPLICA8LE ALARM / TRIP  !

! 4 FUNCTIONAL UNIT TO TRIP / ALARM GPERABLE MODES SETPOINT ACTION ej

1. Containment 4 pe -Q(,3,J-jl 9 gg,g 4 .,

j a. Containment Area (Low Range) 1 2 46k . glC Z.".. & SM 786/f 38-3 j l RE-0002. RE-0003 4g,3,c/ pgJJ4 (

a I b. Containment Area (High Range) 1 2 dit- M M See Ih//l'I'I j RE-0005. RE-0006 )

c. RCS Leakage Detection

{

i' 1) Gaseous Activity RE-2562C 1 1 1,2,3,4 5 2 x back- 9928

2) Particulate Activity RE-2562A.1 1 1,2,3 ,4 ground 0 1 2 x back- 3R Z D q l , ground .' .i 1 2. Containment Ventilation

.Y a. Gaseous Activity RE-2565C 1 2 1tM//4JV4 f f

1. ** 5#t N' #' ~

i b. Particulate Activity RE-2565A 1 2 2R / f2,3J4f6 4 ** '

Ne Tw#e 5,3-5 h

c. Iodine Activity RE-25658 1 2 AR/t5,g,c*

ii a5sr%We'5 $ Se ,7;ffe g y__y

3. Control Room Air Intake L.

Radiation Level RE-12116, 2 A M /f2 , j5 '/ M tr See kJ/e E3-3 k RE-12117 Su %#r. 5,y 4/

l

4. Volume Reduction Room Selective Syg* '

{t' Cubicle Monitors  %

I 4

/ a. Gaseous Activity ARE-13133C 1 1 [] 27

)

b. Particulate Activity ARE-13133A 1 1 [] 27 f

c. Iodine Activity ARE-131338 1 1 [] 27 I

~

i

. i -

\ . .

I TA8tE 3.3-6 (Continued) k RADIATION MONITORING INSTRt20ENTATION FOR PLANT OPERATIONS g MINIMUM l

E CHANNELS APPLICABLE ALARM / TRIP MEA EMENT .

Q w

FUNCTIONAL UNIT OPERA 8tE M00ES SETPOINT ACTION

{

5. Process Monitors  !. }

I'..

jL Noble Gas Effluent Moni s f

a

1. Radwaste Building f.

Exhaust System 1 1, 2, 3 & 4 ( rad /hr 1-108 uC1/cc 30 f

11. Auxiliary Buildir.g '

(

}

Exhaust System 1 1, 2, 3 & 4 ( ) rad /hr 1-108 uC1/cc 30 R*

111. Steam Safety Valve Discharge 1/ valve

\ 1,'- 3&4 ( ) rad /hr

/

1-108 uC1/cc 30

~

h tv. Atmospheric Steam Dump Valve '

Discharge 1/va 1, 2, 3 & 4 ( ) rad /hr 1-108 Al/cc 30 .

A

v. Shlald Building y Exhaust System 1 1, 2, 3 & 4 ( ) ad/hr 1-104 uC1/cc 30 y

' n vi. Containment Purge & 5 Exhaust System 1 1, 2, 3 & 4 ( ) rad /hr 1-10s uCl/cc 30 L r.

vii. Condenser Exhaust (

System 1- 1, 2, 3 & 4 ( ) rad /hr 1- 5 uC1/cc 30

{

• Alarm / Trip Setpoi of 10 rad /hr is acceptable.

s LB .

A * ,i

.y y

~ _ . . . _ _ -

. TA8if 3.3-6 (Continued) ,

~

TA8LE NOTATIONS

• "I ejON o et/ of l49h eA*r //~fschdW

- =  : :=. . :..; .__. . ..... ... .

D t'/p /MHeat nWf a/~ //%er%bd (t4/ 0f nedneerserf af /kas(r ow f,y,ngyj,yfnq f f

, :1 cx: : . e.. c . .. - ,_ # 2 r -

ACTION STATEMENTS g fg 4 g ACTION -

With less1 hem the OPERA 8LE requirement,

."- z, xc.'. .x ;.i.. C. ^ '..i. ;;..^

._;.^. .. ,_ :-f Y

??Ho%vw ert af .5)wdft2*/io r 3, % 6.34N3GklMcTAW/.

. IACTION 27 - Wiir.h the number or ortaABLE channels one less than the Minimum 7 Channels OPEAA8LE requirement, within I hour isolate the Control Roon Emergency Ventilation System and initiate operation j of the Control Room Emergency Ventilation System in the I rteirculation mode.

i ACTION 28 - With less.than the Minimum Channels OPERA 8LE requirement, opera-l, tion may continue for up to 30 days provided an appropriate .

l portable continuous monitor with the same Alarm Setpoint is t

, I provided in the fuel storage pool area. Restore the inoperable .

I I monitors to OPERABLE status within 30 days or suspend all

! operations involving fuel movement in the fuel storage pool I areas. <

t

) ACTION 29 - Must satisfy the ACTION requirement for Specification 3.4.6.1.

/ ACTION 30 - With the nwber of OPERA 8LE Channels less than required by the 1

Minimum Channels OPERA 8LE requirements, initiate the preplanned

{ alternate anthod of monitoring the appropriate parameter (s),

! within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1

1) either restore the inoperable Channel (s) to OPFMBLE

status within 7 days of the event, or l

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following

! the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring i

the system to 0PERABLE status.

! s 1

1 I

j l .

V0GTLE - UNIT 1 3/4 3-45 T' App 34 W

r I - ,

l TABLE 4.3-3 ,

6 RADIATION MDNITORING INSTRWENTATION FOR PLANT 4 . OPERATIONS SURVEILLANCE REQUIREE NTS E

e ANALOG l g CNANNEL MODES FOR WICH j CHANNEL CHANNEL

• OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED

' ]

1. Containment i 3, g gjp ef, y_ g, ,

a. Containment Area (Low Range) 4  :: M -

All ll RE-0002, RE-0003 g gjf, ej,y_ g

b. Containment Area (High Range)  ? 1 M -

Ali RE-0005, RE-0006  !

c. RCS Leakage Detection

1) Gaseous Activity RE-2562C S R M 1,2,3,4

2) Particulate Activity'RE-2562A S R M 1, 2, 3, 4

$ 2. Containment Venttiation '

QN 4,J -2 ' -'

Y a. Gaseous Activity RE-2565C Ali.

g . Set 37 de ,4,3-t-

h. Particulate Activity RE-25654 =S - n . . ).

j a "fa W e Af. 5 - 2.

c. Iodine Activity RE-25658 .

n n hii , ,

3. Control Room Src 75Me%3-L Air Intake Radiation Level , -

2 N -hii -

"4. Volume Reduction Room Selective , N Cubicle Monitors

a. Gaseous Activity ARE-13133C S R M *

• i

b. Particulate Activity ARE-13133A 5 R M

• Iodine Activity ARE-131338

• j c. 5 R M t TABLE NOTATIONS

• 0uring operation of the Redwaste Solidification System.

9

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ e -_ _ _ _ _ _ _ _ _ _ - _ _ _ __ _ ___ _-_

' L

, / j l

, TABLE 4.3-3 (Continued)

RA01ATION MONITORING INSTHMENTATION FOR PLANT  :

g OPERATIONS SURVEILLANCE REQUIREMENTS - /

ANALOG E CHANNEL M00ES FOR lef!CH '

4 CHANNEL CHANNEL OPERATIONAL SyRVEILLANCE e FUNCTIONAL UNIT CHECK CALIBRATION TEST p

IU 5. Process Monitors

'\N .

~

,/

/15 REQUIRED Noble Gas Effluent Monitors

1. Radwaste Building

'/

[ -

s g

Exhaust System S M 1, 2, 3 & 4 g

'\ s R 1

11. Auxiliary Building 'N '-

1, 2, 3 & 4

[

R Exhaust Systaa S R>

M .

• 'e I Steam Safety Valve '

Y g

111.

Discharge S [R M 1, 2, 3 & 4 j' iv. Atmospheric Steam '

f Dump Valve a Discharge [

S R M 1, 2, 3 & 4 ,.

v. Shield Building '

Exhaust Systee S R M 1, 2, 3 & 4 1 I

vi. Containment Pur &

(

Exhaust Syst S R M 1, 2, &4  ;

s vii. Condens xhaust Syst S R M 1, 2, 3 & 4 .

f

• Acce ble criteria for calibration are provided in Table II.F.1-3 of NUREG-0737. I 5 *' I A ,

• E .  :

9

.p v

4 e

u._ . _ _ .__. _ . , _ .

TA8LE 3.3-9 REMOTE SHUTDOWN SYSTEM Minimum I Channels Readout Channels Instrument Function Location Available Ooerable s =

1. Source Range Neutron Flux A 1 NI 31E 1

2. Extended Range Neutron Flux 8 1 NI 13135 C&C ,

1 RCS LP Cold Leg Temperature A. 8 1/ Loop 1/ Loop 3.

Loop 1 TI 04130 (Panel A)

Loop 2 TI 04230 Panel 8 Loop 3 TI 04330 Panel 8

- Loop 4 TI 04430 Panel A

4. RCS Hot Leg Temperature A 2 2 Loop 1 TI 0413L Loop 4 TI 0443C 4

5. Core Exit Thermocouples 8 2 2

. Loop 2 Core Quadrant . TI 10055 Loop 3 Core Quadrant TI 10056 .

6. RCS Wide Range Pressure A. 8 2 2 Panel A PI 405A Panel 8 PI 403A

7. Steam Generator Level' A. 8 1/ Loop 1/ Loop Loop 1 LI5018(PanelA)

Loop 2 LI 5028 (Panel 8) -

)

Loop 3 LI 5038 (Panel 8) ,

Loop 4 LI 5048 (Panel A) i

8. Pressurizer Level A. 8 2 2 Panel A LI 459C Panel 8 LI 460C

9. RWST Level L 1 LI 0990C 13

10. BAST Level L 1 PI-101152 13

11. CST Level L 2 23 Tank 1

- LI 5100 Tank 2 LI 5115 l

1. A - Remote Shutdown Panel PSDA 8 - Remote Shutdown Panel PSDB L - Local Indication

2. Graph will be provided to detemine level from pressure reading.

3. Alternate local level indication may be established to fulfill the minimum channels OPERA 8LE.

V0GTLE - NIT 1 3/! 3-58

g TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 7 SURVEILLANCE REQUIREMENTS E

9 CHANNEL CHANNEL

- INSTRUMENT CHECK CALIBRATION

1. Source Range Neutron Flux M R

2. Extended Range Neutron Flux M . R

3. RCS LP Cold Leg Temp M R

4. RCS Hot Leg Temp M R

5. Core Exit Thermocouples M R f

6. RCS Wide Range Pressure M R

7. Steam Generator Level Wide Range M R o

8. Pressurizer Level M R

9. RWST Level M R

10. BAST Level M R

11. CST Level M R e

• e e TABLE 3.3-13 ,

RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATI0'N b ,

E MINIMUM CHANNELS 5

-4 INSTRUENT OPERABLE e APPLICABILITY ACTION H 1. GASE0US WASTE PROCESSING SYSTEM Noble Gas ' Activity' Monitor -

q a. i .

Providi ' Alarm and Automatic Terminat on of Release (ARE-0014) 1 45

b. Effluent Systen Flow Rate Measuring Device (AFI-0014) 1 *** 46 -

2. GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System M a. Hydrogen Monitor 1/recombiner ** 49,

b. Oxygen Monitor 2/recombiner ** 49

3. Condenser Air Ejector and Steam Packing Exhauster System .

a. Noble Gas Activity Monitor 1 *** 47 (RE-12839C)

~

b. Iodine Sampler 1 *** 51 (RE-128398) ,

c. Particulate Sampler. 1 *** 51 (RE-12839A)

I d. Fiow Rate Monitor ~ 1 46

, so (FI-12839)

• .l

e. Sampler Flow Rate Monitor *** 46 g (FI-12839) 1 ,

^

TABLE 3.3-13 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ,

E s ,:

' I, MINIMUM CHANNELS E INSTRUMENT OPERABLE APPLICA8ILITY ACTION  !

A P w 4. Plant Vent

a. Noble Gas Activity Monitor 1

• 47, 48 -

f (RE-12442C or RE-12444C) 1

b. Iodine Sampler 1

• 51 I (RE-124428 or RE-124448) ,

c. Particulate Samoler 1

• 51 ,

(RE-12442A or RE-12444A) I R

d. Flow Rate Monitor 1 -, 46 [l (F1-12442) !i Y

• M e. Sampler Flow Rate Monitor 1 46 (FI-12442 or FI-12444) l

, ,g.!

5. Radwaste Solidification Building  !

a. Noble Gas Activity Monitor (ARE-0026C) .

1

• b .y

i.

/

b. Iodine Sampler 1 *- 51 L (ARE-00268) t

c. Particulate Sampler

• 1 51 1 (ARE-0026A) .

I d. Flow Rate Monitor 1

• 46 ee (AFI-0026) g e. Sampler Flow Rate Monitor 1 * ,

46 p;

[.

(AFI-0026) . >,

~

'y

,r .

li l.'

TABLE 3.3-13 (Cantinurd)

TABLE NOTATIONS

• At all times.

• • During GASEQUS WASTE PROCESSING SYSTEM operation.

• ***During radioactive releases via this pathway.

ACTION STATEMENTS ACTION 45 - With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup. .

Otherwise, suspend release of radioactive affluents via this pathway.

ACTION 46 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 47 - With the number of channels'0PERABLE less than required by the Minimum Channels OPERASLE requirement, effluent releases via

, this pathway may conti $ provided grab samples are taken at least once per 12 hourt and these samples are analyzed for ~

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

ACTION 48 - With the number of channels OPERABLE less than required by the Minimum D snnels OPERA 8LE requirement, immediately suspend .

PURGING of radioactive affluents via this pathway.

.,.,,. .. _ us.m .<_ _ m _ a _&____i_ ...... e n . .m__ ___..,__2 6., .u.

s ';_- ' m__:n ; ;.r..; :_n;- ::: -- :-- r, - - m  ;-1..;.e..,

. .. ;;; ;_:x';;'J ' ::,;=- ' r - "1'r'LT ': ' T" "' ""l"

~1 E _ n' r : '; r _" z ' I' c J :'_r T ' Z C _* ;- ., n , ' K _ - ' _

Z4. ~-- --- - --- - ' - ~ ' ~

;L. . _' . . z ' ~ ' ~ r -

A #b9T Aka FM _ U,AL AL_ ____L___ _A _L_____,_ mRPR ASS P ___ ,___ AL__ ___..,__J kam

"_l _

o ;"'_: _ ,.n _'. ' ,. :."L,"_'_;;'_e'i'"_3--

-". .I ' '_ r ;r _ ' ;rai: '

cy:^

g,__

cr . : ; x'd-d ;ro --

,__ y _

u,

'n r; tr,-

7, rf7 3.r '_;rf _ .

- r = =; =:t' 1;. ='d:d ; ret :-- 'n are t;'a= xd x:!ynd-t ';n t x;; ;;r ' 'd.7- d.-!:; 2;;n -in; ;;;;.ti n rd :t 1:Ct

=:: ; r '. r -- f r ' -- - * '-- -- - - -" - n V0GTLE - UNIT 1

~~

3/4 3 MR 84 5*

Insert for page 3/4 3-7 ACTION 4 - a. With the outlet oxygen monitor channel inoperable, operation o9 the system may continue provided grab samples '

are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the oxygen cor.4entration remains less. than 1 percent.

• s. .

b. With the inlet oxygen monitor inoperable, operation may continue if inlet hydrogen monitor is OPERA 8LE.

I

c. With both oxygen channels or both of the inlet oxygen and

" inlet hydrogen monitors inoperable, suspend oxygen supply to the recombiner. Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentra-tion remains less than 1 percent.

ra p n d s , w x a urum C 4 ,w h a o u s u g un w ~ 6 supw ayer supp/y a Me. reca*16w. &v//iw of our/ ryas ./o ftie 17 S/a'r 'W7 0*'/A!M*- /'"WW t

J/ab samples are faken ad and/yr& Gf /Ms/

d ouhitpvmee 4hua yarray ym% o,-

af pe ciumy/

z+ awr dwg. sMe ye,g,w a+1He oxyy*1 wiwriabM nudos /nr k ifkeetf.

(

1

~

9

TABLE 3.3-13 (Continued)

TABLE NOTATIONS (Continued) .

. i ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases via )

the affected pathway may continue provided samples are contin-unusly collected with auxiliary sampling equipment as required in Table 4.11-2. ,  !

. $. f) - N IIC ^^ ^^ 27 Cf C. 2.^.^.2)C $f(f[$ ^^C )CC

.. I"^ ~[ ^,2i "[I 05: "

. ._ .<_'n'--- Ch::::)C 0""."f."'I

'r

.t, :::;: I cr;;:. :r;;g e

e l

1 l

l V0GTLE - UNIT 1--- 3/4 a-77 APR 241986

. o _ . _ _ -. ____ _ . . . . _ _

o .

,' TABLE'4.3-9 (Centinued) j g , RADI0 ACTIVE GASE0US EFFLUENT NONITORING INSTRUNENTATION SURVEILLANCE REQUIRENENTS E i ANALOG I E CHANNEL MODES FOR WHICH I Q CHANNEL - SOURCE CHANNEL OPERATIONAL SURVEILLANCE l INSTRUNENT ,

CNECK CHECK CALIBRATION TEST IS REQUIRE 0

4. Plant' Vent ,

a. Noble Gas Activity Monitor 0 M R(3) Q(2) *

(RE-12442C or RE-12444C)

~

b. Iodine Sampler W N.A. N.A. N.A. *

(RE-124428 or RE-124446)

c. Particulate Sampler W '

N.A. N.A. N.A. *

.R. (RE-12442A or RE-12444A) 8

+ -

/ i Y d. Flow Rate Monitor D N.A. R Q 3 (FI-12442)

e. Sampler Flow Rate Monitor D N.A. R Q ,

(FI-12442 or FI-12444) g

5. RadwasteSolidiilcationBiiiiiiing,

a. Noble Gas Activity Monitor D M R(3) Q(2)

• i (ARE-0026C) '

l

b. Iodine Sampler W N.A. N.A. N.A. * -

/ (ARE-00268) +

c. Particulate Sampler W N.A. N.A. N.A. *

'I (ARE-0026A) il 5 d. Flow Rate Monitor 0 N.A.

• e R Q ll (AFI-0026) ij 3

e. Sampler Flow Rate Monitor 0 N.A. R Q f

(AFI-0026)  !,:

y

, , t.

_. a . ~.. .. .. a-.. w w w m.-- m. aa. ,: -

--.:.- m.sq y.&.. -

l t

~

, . TABLE 4.3-9 (Continued) l TABLE NOTATIONS At all times.

• • During GASEQUS WASTE PROCESSING SYSTEM operation. l

• • • During Releases via this pathway.

(1) The ANALOG CHANNEL OPERATIONAL TEST sha11 also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alare/ Trip Setpoint, or

b. Circuit failure, or -

c. Instrument indicates a downscale failure, or ,

i

d. Instrument controls not set in operate mode. {

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control I room alare annunciation occurs if any of the following conditions exists: '

a. Instrument indicates measured 1cvels above the Alarm Setpoint, or l

b. Circuit failure, or j

1

c. Instrument indicates a downscale failure, or i

d. Instrument controls not set in operate mode. 1 (3) The initial CHN#fEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (N85) or using. standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related

. to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include yse o standard les lif d(tmh /cd-up; gne e, setti (tm .rs, netfilt;ur

'iYf, _ _,__ _. _ _

Fwis

- - &d:r4N'"halikien.,

-- -.; n-, EMFmeMry

---:-e 7 J M< hyshy*r au/yw ,

l (5) includeuse of sta #

mThe - CHANNEL CALIBRATION r- ypu shall e,arsnGec the/we4recam*ndard 1enda:hns.r. gasJ>t samalas

<ddiffois in A(CW28 q l a.

%M ps.:s*Qk ons.;fg. ,l dee W volume fM 0xyy en , bdwr nifa,y.,, i One volume percent oxygen, balance nitrogen, and SAw// be s.ted in f4r celibinrfter le Cleef' /Merihr e /44e.Ns on m m/ow.

b. Four volume percent oxygen, balance nitrogen. /

maa41ses V0GTLE - UNIT 1 3/4 3-80

n . . -. . w.a. - - - - - -

. . . . . . . . . . ~ . . . K. . . - . . :, . ....:.

l INSTRUNENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS  !

LINITING CONDITION FOR OPERATION 3.3.3.12 The high energy line break instrumentation listed in Table 3.3-14 l shall be OPERABLE. 1 APPLICA8ILITY: As noted in Table 3.3-14.

ACTION:

a. With the number of OPEitABLE electric steam boiler isolation instruments less than required by Table 3.3-14, restore the inoperable instruments to OPERABLE status within 7 days or suspend operation of the electric staan .

o 0PE K E status. W M W b.

oY[h"/dN N#N2/If*hE4d'.s om With the number of OPERA 8LE steam generator blowdown line isolation instru-ments or letdown line isolation instruments less than required by Table 3.3.14, restore the-inoperable instruments to OPERABLE status within 7 days or be in NOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> a..d in COLD SHUTDOWN with the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RFOUIRENENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG. CHANNEL OPERATIONAL TEST at least once per 18 months. -

l l

9 V0GTLE - UNIT 1 3/4 3-81 Ei APR 84 E

-_ __g_n --

a.:c 9 .. :

_. . _ 2 - a N

. TABLE 3.3-14 HIGH-ENERGY LINE BREAK INSTRUMENTATION solation .

Minimus AppIicable netion Channels Operable Mo' des _

1. Ele ric Steam '-

1/ channel ,

Boile Isolation ,/ -

2. Steam Ge erator Blowdown ine 1/ channel j/ 1,2,3,4 Isolation

3. Letdown Line 1/ channel 1, 2, 3, 4 -

Isolation

/

/

. /

I

/

/

/

/

/

I

/

/

\

" Required ddring all modes when electric steamperation. boiler is in o\

V0GTLE - NIT F 3/4 3-82 E I4 E

f .

I4

.. TA8LE 3.3- W HIGH-ENERGY LINE BREAK INSTRUMENTATION Isolation Instrument Minimus Applicable

, Function Channel Channels Coerable Modes

• 1. Electric St'eam TE 19722A R052 . 1 Boiler Isolation TE 19723A R052 TE 197228 RC41 1 TE 197238 RC41 1

• TE 19722C (RC64)

TE 19723C (RC64) ,

TE 197220 RC66 1 TE 197230 RC66 FT 19722 1 FT 19723 TE 19722E RC95

• 1 TE 19723E RC95

2. Steam Generator TE 15212A (R808) 1 1.2.3.4 Blowdown Line TE 15216A (R808)

Isolation TE 152128 (RC106) 1 1,2.3.4 TE 152168 (RC106)

TE 15212C RC107 1 1.2.3.4 TE 15216C RC107 TE 152120'(RC108) 1 1,2.3.4 TE 152160 (RC108)

FT 15212A (Loop 1) 1 1,2.3.4 FT 15216A FT 152128 (Loop 2) 1 1,2,3.4 FT 152168 FT 15212C (Loop 3) 1 1.2,3.4 '

FT 15216C FT 15212P (Loop 4) 1 1.2.3.4 FT 15216P

3. Letdown Line TE 15214A 7 1 1,2.3.4 Isolation TE 15215A 7 TE 152148 (A08) 1 1.2.3.4 TE 152158 (A08)

. TE 15214C A09 1 1.2.3.4 TE 15215C A09 PT 15214 1 1.2.3.4 PT 15215

• Required during all modes when electric' steam boiler is in operation.

1 V0GTLE - UNIT 1 3/4 3-86

TABLE 4.11-1 (Centinu'd)

• TABLE NOTATIONS (Continued) l (3)The principal gamma emmiters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not Roan that only these nuClides are to be Considered. Other gamma peaks s that are identifiable, together with those of the above nuclides, shall l also be analyzed and reported in the Semiannual Radioactive Effluent '

Release Report pursuant to Specification 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix 8. Revision 1. June 1974.

(4)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 l method of sampling employed results in a specimen that is representative of the liquids released. )

(5)A continuous release is the discharge of ifquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.4 . -. - -

7 (0)To be representative of the quantities and concentrations of radioactive {

materials in liquid effluents, samples shall be collected continuously in '

proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the affluent release.

i

- 7~his wi// irof du cer;;c/ene/ a cm/d1Mm ft/4mre oiWetfd f is a c+s ksrect,ornmv 6neinnvy /cok. t<hfor /b-e it *,onnwry

/c Secachtny re/ecsc.,y i / uh7/ bels cuhnous te/ ear <. Ar/77 /4(cfed 4r

/td/ There surved/e/rer wiv/ cm/mM' TM/// /4/ee execs /7de ejue z g.

4> <e } ce," pas /Je Garfi /cr J4sm/ sie sc//

l l

V0GTLE - UNIT 1 3/4 11-4 APR 34 W i

RADI0 ACTIVE EFFLUENTS -

DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER 0F THE PU8LIC from radioactive

, materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited: ' -

a. During any calendar quarter to less than or equal to 1.5 areas to the whole body and to less than or equal to 5 areas to any organ, and

b. During any calendar year to less than or equal to 3 areas to the whole body and to less than or equal to 10 areas to any organ, APPLICA8ILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive asterials in liquid affluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. TM: !;::* 9 "- :-* 2:? ? ':: ' .f.cf:. '1; r.;

" ^

- :r?'- ' rdi ' n'::? :: !;::: :f r.; '*  ::::::, ::d C ) th: d ';?:;'::! i- ::t . "".t Y 'ni'.., J .: :;;?';; rith

--:;ft: '2.: 7: :' - .t: :? 'O "T! "_ ; l'!, ut " 'd':;; ":tr

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

. l SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days. -

V0GTLE - UNIT 1 g 3/4 11-5 APRS4IM6

l l

l RADI0 ACTIVE EFFLUENTS -

LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION

, 3.11.1.3 The Liquid Radwaste Treatment System ah'all be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1) would exceed-evet aren to the whole body or 0.2 aren to any organ in a 31-day period. Lg APPLICA8ILITY: At in11 times.

ACTION:

' a. With radioactive liquid waste being discharged without treatment and

. in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was b'inge discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action (s) taken to restors the inoperable equipment to OPERABLE status, and

3. Summary description of acti6n(s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not app 11 cable.

_ _ _ SURVEILLANCE REQUIREMENTS __

l

4. n.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at leas.t once per 31 days in accordance with the methodology and parameters in the 00CM when Liquid Radweste Treatment Systems are not being ,

fully utilized.

1

4. n.1.3.2 The installed tiquid Radweste Treatment System shall be considered OPERA 8LE by meeting Specifications 3.11.1.1 and 3. u.1.2.

V0GTLE - UNIT 1

• Z~ 3/4 u-6 pg 3 4 W

2 . -.a _ -

._ _ w :_ _. w _, _

RADI0 ACTIVE EFFLUENTS LICUID HOLDUP TANKS ~

l

_. .__ LIMITING CONDITION FOR OPERATION l

3.11.1.4 The quantity of radioactive material. contained in each outside temporary tank shall be limited to less thart or equal to 10 Curies, excluding tritiumanddissolvedorentrainednoblegasesQt, i APPLICABILITY: At all times.

. ACTION: -

oah,de hapwat9

a. With the quantity of radioactive material in any of the a m /

tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, 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, and describe the events leading to this condition *in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l I

_ _ _ SURVEILLANCE REQUIREMENTS eHher 4.11.1.4 The quantity of dioactive material contained in each of the above j listed tanks shall be de ruined to be within the above limit by analyzing a i

, representative sample of he tank's contents at least once per 7 days wh l radioactive materials are being added to the tanV or eddi 421/c/ /de,en tzadisc}ife aufvte/ friar & ilt noW/Har k & kK 1

V0GTLE - UNIT 1 E 3/4 11-7 APR 24 W6

TABLE 4.11-2 RA010 ACTIVE GASEGUS WASTE SAMPLING AND ANALYSIS PROGRAM l

E i:

MINIMlM LOWER LIMIT OF h DETECTION (LLD)(II E

E SAMPLING ANALYSIS TYPE OF Q GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCl/ml) [;

a Each Tank' {ach,, p , , Pridcipal Gamma Emitters (2) 1x10 4 Grab Sample ,;,,,,,

2. Containment Purge P P 24" or 14" Each PURGE (3) Each PURGE (3) Principal Gamma Emitters (2) 1x10 4 Grab Sample M H-3 (oxide) 1x10 s j

3. a. Plant Vent M(3),(4),(5) Principal Gamma Emitters (2) 1x10 4 [

1:

8 Grab Sample M I3) -

, [

• H-3 (oxide) 1x10 s h b. Condenser Air M(5) Principal Gamma Emitters (2) 1x10 4

• Ejector & Grab Sample g Steam Exhaust 1x10.s H-3 (oxide) , p f

M~ Principal Gamma Emit drsI2I EID i

[ c. Solidtfication 2 Bldg, Radwaste Grab Sample M l M ea, Others

. ---- - - - - i

4. All Release Types Continuous (6) y(7) I-131 1x10 18 as listed in 1.,

and 3. above 2.* Charcoal f r

3 ,j , ,

Continuous (6) y(7) Principal Gamma Emitters (2) 1x10 81 -

Particulate i Sample  !

g I

• Continuous (6) M Gross Alpha 1x10 18 y Composite Par-ticulate Sample Continuous (6) Q Composite Par-Sr-89, Sr-90 . lx10 18 jg j ticulate Sample t I

c

l . .

TA8tE 4.11-2 (Continued) ,

TABLE NOTATIONS (Continued)

(2)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133s, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, '

Zn-65, Mo-99, I-131, Cs-134, CS-137, Ce-141 and Ce-144 in Iodine and

, particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma pteks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 in the format outlined in Regulatory Guide 1.2, Appendix 8 Revision 1, June 1974.

(3}5ampling and analysis shall also be performed following shutdown, startup, ,

or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a l 1-hourperiod.g j I4)Tritive grab samples shall be taken 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 l

~

refueling canal is flooded. j (5) Tritium grab samples'shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is i in the spent fuel pool. i (0)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3. n.2.2, and 3. n.2.3.

(7) 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 sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 155 of RATED THERMAL POWER within a 1-hour period 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 /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if: (1) analysis shows that the DOSE

.. EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that affluent activity has not increased more than a factor of 3.

7~}1/s u& tor er/ 0(wr ifp/ 92 / // (f) ot/db fS/2 SkeRMlbfl$2, l Au $tguiwee z-m cuc hupai, a depiwasy ess/d i G- Ac sw/ 4owrc/ intre Hun 4 rGcfor ef 3; ditc/(y

\ $lc ris4/6 f4J Afsnll"r $bHU $W 6$&&ff GC,bW I lyr ty? i3crwrm/ nda Man a Scheof J.

i V0GTLE - UNIT 1. E 3/4 n- H gpg 34 W I

l l

RADIOACTIVE EFFLUENTS -

GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 2.0 x 105 Curies.of noble gases (considered i as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all. additions of  :

radioactive. material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank l contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6.lThe quantity o.f radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 44 7ds/s hours when radioactive materials r : t i ; added to the tan V /o A c h ef /

/DR dMrs chfnyt v'1(efM*'NW 9 d}si 1.//. 2.& 2 5 7k. **er/ oftotArmen'/*rgjor/ue//s#wc. (pi9}

a,ga,9 a saseesw-w ww w n-a -ic ps dey /arit s/re// be o'e/esvrin</ A he uiU4e weak >e brif af /ec/ osce,ser 24 bo"6' al/im rador& ve insfenats Asn beer adkd' /* Me fewk in thepreviaw zf40uin V0GTLE - UNIT 1 2 3/4 11-16 APR 24 m

n. . . . . . . . - e n. . .. n-m . ,

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING -

/

3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION-

, 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1. '-

APPLICA8ILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitcring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Surveillance Report required by Specification 6.9.1.3,, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

ccn HryruP' a  :

b. With thettlevel of radioactivity as the result of plant affluents in {

an environmental. sampling medium at a specified location exceeding i the reporting levels of Table 3.12-2 when averaged over any calendar i quarter, prepare and submit to the Cornission within 30 days, pursuant l to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluent's so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.u.1.2, 3.11.2.2, or 3.H.2.3. When more than one of the radionuclides in Tabl,e 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1? ed$ centration (2) reporting level C ), ing level (2)

+ ***>- 1.0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

• to a MTMBER OF THE PU8LIC from all radio-nuclides is equal to or greater than the calendar year limits of Specification 3. H.1.2, 3. u.2.2, or 3. u.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in tuch an event, the condition shall be reported and described in the Annual Radiological Environmental Surveillance Report required by Specification 6.9.1.3.

• The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

CarAmofo relm M ofMe oi / M/VjJ/A#/t, W4460 W/lf-ny be etwl{we ahypryrion. ktei%2, resu/h a/ m saa dir-dos a

. shot / be cay >/efaf ef & mrbu.r/ /rme cor;%f- ric an4 M but in my wit uiMin Jo a'y;.

= . APR 24 886 V0GTLE - UNIT 1 3/4 12"1 l

~~ -

-- u......

RADIOLOGICAL ENVIRONMENTAL MONITORING .

! LIMITING CONDITION FOR OPERATION ACTION (Continued) l c. With milk or Vt *::_qLNiM

. I n C ;;;;t e h samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring-Program given in the 00CM. The specific locations from which samples were

, unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.14 submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the 00CM l including a revised figure (s) and table for the 00CM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples,

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3. u-1 from the specific locations given in the taole and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of i Table 3. u-1 and the detection capabilities required by Table 4. u-1.

I d

e

=

. .ii .

$PR 34 % l V0GTLE - UNIT 1 3/4 u-2 1

l

e TABLE 3.12-1 1 RADIOLOGICAL EWIR0000 ENTAL MONITORIllG PROGRAM IIUMER OF l REPRESENTATIVE E EXPOSURE PATitiAY SAMPLES AND SANPLING AND TYPE AND FREQUENCY 4 AND/OR SAMPLE SAMPLE LOCATI0llS III COLLECTIO11 FREQUENCY OF ANALYSIS

1. Direct Radiation (2) Thirty lsix routine monitoring Quarterly. Gamma dose quarter 19 J'l ,

stations-(GM4A40) elther with ,

two or more dosimeters or with

~

one instrument for measuring and

recording dose rate contirasously,

placed as follows

An inner ring of stations, one in

each meteorological sector in the general area of the SITE BOUNDARY ~,

$ 48844 H Gi M An outer ring of stations one in 4 each meteorolog[ cal sM in them.(3 to Falley~ range e

! from the site (S M FSAGS); and i

The balance of the stations 40A0>0 MG) to be placed in special interest areas such 3 as population centers, nearby residences, schools, and in one 2-or two areas to serve as control stations. .

8 99

.g

1 ,

i TABLE 3.12-1 (Continued)

RADIOLOGICAL E WIRefetENTAL MONITORING P90 GRAM b NU MER OF j REPRESENTATIVE 5 EXPOSURE PATIRdAY SAMPLES AND SAMPLE LOCATIONSgg)

SAMPLING A M TYPE AND FREQUENCY Q AND/0R SAMPLE . COLLECTION FREQUENCY OF ANALYSIS N 2. Airborne .. .,

b Radiolodine and Samples from five locations Continuous saapier oper- Radioiodine cannister:

)i Particulates -

ation with. sample collec-tion weekly, or more I-131 analysis weekly.

l' Three samples -W from frequently if required by close to the three SITE dust loading. Particulate Sampler:  ;

]

arm naaY locations, in Gross beta radioactivity i ,

difforent sectors; e64he analysis following i u _m__. __i_....._2 ----s

_;. _ _ .: _-:: n _; s ' , filter change;(3) and )

, g --- . . - - . _ - - - , .

. g.,,, g ,,g p g e ,,,jyg g ,w.

4

• of composite (by M One sample from the vicinity location) quarter 1 :

i a of a community having the J highest calculated annual ,

I average groundlevel D/Q; and One sample M from a control.

i location,asforexample46-4eofwfuk/Ag cul/cr af' -adHun f10 to 20 allerdistant l and in the least prevalent

1. wind direction.

i 3. Waterborne

a. Surface (5) One sample upstrean M . Composite sample over Gamma isotopic ana)ysis IN f C s l One sample downstream M . 1-month period.(6) .

, , rerlyl 1

^ #-~~~

i. "T

_  : ~_ .I I- .~ h ". a --- ^ ^^: : _T;;; _- _

t..!,. h;^ 2f h

f-3

= , n .  :, n 1: u , -_ u - = = "'----"----%

i  : _..- _--_ , , _ _ . _ *n. ,

.w w

- 4 TABLE 3.12-1 (Continued) g. j gf ,gg RADIOLOGICAL ENVIR0lelENTAL MDNITORING PROGRAM ( G M M N F b 4/* M eW i g;; j .'

! NUDGER OF l REPRESENTATIVE i E EXPOSURE PATIAdAY SAMPLES AND' SAMPLING AND TYPE AND FREQUENCY ,

Q SAMPLE LOCATIONS III COLLECTION FREQUENCY l OF ANALYSIS

) AND/OR SAMPLE ,

) 3. Waterborne (Continued)i .,,,,,.,,ii a t . ,, ,, ,e -

pg

[1 guo. , m . af < ' 's,. , , . , r b/. Drinking 4me.samplesef each of.one.to ,,, Composite sample over I-131 analysis on each three C."_; ^^O of the nearest (6) "

-  ::! t when the dose

• 'd/*

/ /ads

;;!':: that could be affected by its discharge. [_"" ] , g, formed; monthly com.

r-calculated for the con-Sumption of t h water

/Ta* positeotherwisat.fa'mf is gmater than 1 area h samples a contml / per year Composite location M 744 S**/ f-0/ Rn/J4ec/

sdPW A7 dtM net /F for gross beta and gamma

-/neq4eso7//M/ eW/7 isttopic analyses (4)'

g g g ,g s y . ,g jj jP/ y monthly. Composite for Y f ' j ,*

g tritium analysis quarterly.

E Sediment One sample from downstream area t'4ealannua11y. Gauna isotopic analysis II)

Cf. sesfiannually.

from with existing or potential Shoreline recreational value M .

{ 4. Ingestion

a. Milk Samples fron'ailking animals Semimonthly when Gamma isotopic I4I aid in three locations O C " f, n'r-?! : 27 ; ^ r q I-131 analysis semi-

! a smik 'withiPMa distance having the  :: '2?; d . ;,h monthly N ,

I highest dose potential. If 2N 0 ? :'272; 2:2'l!F i

there are none, then one O' 2' t:; ^ !--.

i sample from allking animals in each of three areas

• C: - LO between 4-6e 3 fa e/w/- Sm//s.r g ede-distant where doses 3 are calculated to bj p ater

f.han 1 ares per yr.

l

• - V One sample from milking' animals g

,) y ,,,,.j,, ggj,f. ,,.j, f gO e,rg 74 I at a control

. . . . l.ocation W

.....,,_.u l

3EE h 2255 wind directio.haf/45W//##'4/""-

e

, TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIR00 MENTAL MDNITORING PROGRAM N DESBER 0F REPRESENTATIVE E EXPOSURE PATmeAY SAMPLES AND SAMPLING AND TYPE Als FREQUENCY Q AND/OR SAMPLE SAMPLE LOCATIONSgg) COLLECTION FREQUENCY OF ANALYSIS

'g

4. Inge'stion (Conti h 7

lfII 8 '/'*3 f aF .

b. Fish -end done sample of emen-commercially Sample in season, or Gamma isotopic analysis (4)

':::rt:- and recreationally important semiannually if they on edible portions.

6eetes- species in vicinity of plant are not seasonal.

// /u/ 4,e s /, of 7 A8,5,c$.rge area. t: m 't_) .

a14/a.,,v3 f .5 cia; /d sample of-ses[a species in o/gw/ da 4/p. /t/4/f areas not influenced by plant y I discharge '"il! 'h _ ,. gg,., f., 3 ,

) c. Seed  ?:: :- ;1: Of :::5 prir.:!s t- "t t':: # i: .:et-

. . Gamma isotopic analyses II Produets -c!::; ef f:: pr:f' ::,e .f.w _

on edible portion.

Y Cvass (~ ha,3

- ; :::: th:t i; tritiip;ted-La4 gy = g 7 g;; g, g ; 7,,,;;_ ,

. ... m..... <--_m_- ,

5;. - _'C r ' ,,'X . :- i g jw, - .--- -.

l o'5//' /a m // M J '18d M d -f- ;1:: cf thr:e differer.t Monthly during Gamma isotopicI4) and 1-131 S/T4 SOLWO4A7 /4 h8-M -f irc:f I.w; .. ,_te growing season. analysis.

l c//((Ved/' Sc C/orJ. 't'^^

= E _Zi~- =*t il2h "I .

.ww w u s e ww wvve. Ut t B E EW IW W ti::: ef hir::t prud'::, 4

---~-! r r - : .. r-~' -

k.~.;

/i; i f ;;;'.ik. .:. ..- 1 ; .  ; e ..;.

n.. .- ,____ . . ,.

02: : --1: Of :9 Of th Monthly during Gamma isotopic (4 I- W b/t' Sd /d ##l 4 sieHer' tr::f 1::f .':6te growing season. analysis.

g p/fo/ g /f g o f- t!:: F:r- 15 te 30 % di=-

e. 46dif/ /5 W/7d'/ ' bh..N .N._.b... 5.. N. b_ .[ .

c/fJ/aerc 8.

• - plirs is ,,et p rf:rc : ' ;20 -

. Each saa h locni&1 jil/ be c/tsynefe/ riv be,-

r n991e , C/ Te*u o /46o) a pc W mi 9 \

TAB,L,{3.12-1(Continu-d)

Aa br/a/w/ Mo cerfer08 l

. Me l-b

f TABLE NOTATIONS (1) Specific parameters of distance and direction sectorttfroof : :xt ";

.abone reactot( and additional description where pertinent, shall be pro-vided for each and every sample location in Table 3.12-1 in a table and

' figure (s) in the OIJCM.* Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specificatibns for' Nuclear Power Plants," October 1978, ,

and to Radiological Assessaant Branch Technical Position, Revision 1, l Novesher 1979. Deviations are permitted from the required sampling ,

, schedule if specimens are unobtainable due to circumstances such as I hazardous conditions, seasonal unavailability, and malfunction of-este - l

-meM+ sampling equipment. If specimens are unobtainable due to sampling I equipment malfunction, effort shall be made to complete corrective action I prior to the end of the next sampling period. All deviations from the 'l sampling schedule shall be documented in the Annual Radiological Environ-mental-Surveillance Report pursuant to Specification 6.9.1.3. It is recog-  ;

nized that, at times. it any not be possible or practicable to continue j to obtain samples of the media of choice at the most desired location or '

time. In these instances suitable alternative media and locations may be  ; i chosen for the particular pathway in question and appropriate substitutions s,j tam / 1 made within 30- days in the Radiological Environmental Monitoring Progras, pi/

given in the 00CM. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the 00CM reflect- ~ ,

l ing the new location (s)4with supporting information identifying the cause of the unavailability of tamples for the pathway and justifying the selec-tion of the no.s locatio 1(s) for obtaining samples; or//y wraN//dN//p d/

jiksp Suik Wt rieu locAqfins.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addi-tion to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dcsimeters.

, Film badges shall not be used as dosimeters for measuring direct radiation.

1 (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples ,

is greater than 10 times the yearly mean of control samples, gamma l isotopic analysis shall be perforpsd on the individual samples.

e V0GTLE - UNIT 1.-- 3/4'12-7 APR 34 W

~

l TA8LE 3.12-1 (Continued) .

TABLE NOTATIONS (Continued)

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the affluents from the facility. '

s s.

(5) The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone.

(6) ^ :: ;r't: :---?: ': x: ' d hi tt: ; r t'ty ':;r:t) c' ;;'d :-_ ;' ;

i: ;;;; rt':::? 'a it: ; : .ty O' "'d:; ; fI rI '- *f h ": ::tr.:: i

" :- ; ; - ;hy:d cr !'z f : :;::f:r :t ': r;- :rt::: :" tt:

' ';' d "? r. In th': ; :;r _- $=;-esite sample aliquots .shall be collected l at time intervals that are very short (e.g., hourly) relative to the ,

compositing period (e.g., monthly) in order to assure obtaining a representative sample. .

O) Oi _ .fut.: :- ;'.; :i;?? i_ i d:- to th': : n x ' ^^ ;:f.':- f '  ;

r ' O t'

; ;:: = ' :- : rh:r: t's hydrr !?: ;r:d't-' c- M - e -

; rti:: :: ::'* 9?: M r r.': '::tt:r. -

The dose shall be calculated for the maximum organ and ags gieup, using the methodology.and parameters in the 00CM. p

9) If. harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, samplin s' shall be monthly. Attention shall be paid to including samples of tuberous and root food products.-

(8 ) k snil h enting/ is 4 Cow or ckpy' rdtA:s m,/g g, /js%e;s, C#1somp/ipsy k 5 M tf f flamm4 lt skh)d/c gnc/ sis ;) 11W M'Y'N h b lnJft l herjyl c)/ hdltCb/Of kr hlN, A Sydatofe- au/ysn Air J~ 131 w/// be ,setA% red

. ~

9 V0GTLE - UNIT.1,g; 3/4 12-8 M2496

~

. e TA8LE 3.12-2 REPORTING LEVEL 5 FOR RA010AC11VITY CONCENTRATIONS IN ENVIR0000 ENTAL SAMPLES REPORTING LEVELS b

WATER AIR 8ORNE PARTICULATE FISH MILK F000 PRODUCTS

1. (pCl/1) OR GASES (pci/m8 ) (pci/kg, wet) (pci/1)

ANALYSIS (pci/kg, '

wet)

IU.

H-3 20,000* ,

. Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 -

{

Zn-65 300 20,000 o

Z- -95 400 a Nb - 5 @

I-131 2 0.9 3 100-Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 l'lO 200 30 0 a-140 200 iMNF/M

• For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pC1/1 may be used. .

N

= . .

A e 5

. ,, , m TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONNENTAL SAMPLE ANALYSISII) III

. LOWER LIMIT OF OETECTION (LLO)I }

.s WATER AIRBORNE PARTICULATE FISH MILK A%"F k eel F >4ASONGE SE0lMENT

,[ ANALYSIS (pC1/1) OR GASES (pCi/m3 ) (pCi/kg, wet) (pCi/1) (pC1/kg, wet) (pC1/kg,dp) -

f: Gross 8 eta 4 0.01 ,

H-3 2000*

Mn-54 15 ,

130 Fe-59 30 260

, R Co-5 15 130 Ce-40 15 130 y 2n-65 30 260 ,

Z 95 30Mr a

1. 6@-m' 15 I-131 1 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 ck HO 60 60 a-140 15 * .

• 15 "If no drinking water pathway exists, a value of 3000 pCi/1 may be used.

% Ef' m JM big 4 % f 4 MiUS, a$1/& 0l /5 flll n & Ef14 '

=

De

TA8LE 4.12-1,(Continued) . l TA8LE NOTATIONS a.s p/wrt eM/M155 (1)This list does not mean that on1 hose nuclides are to be considered.

Other peaks that'are identifiabl together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Surveillance Report pursuang to Specification 6.9.1.3.

s s.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental. measuremente shall be in accordance with the recommenda-tions of Regulatory Guide 4.13. ,

(3)The LLD is defined, for purposes of these specifications, as the smallest concentration of. radioactive material in a sample that will yield a net count, above system background, that will be detected with 955 prot, ability '-

. with only 55 probability of falsely concluding that a blank observation represents a "real" signal. -

For a particular measurement system, which may include radiochemical separatten:

4. s b

LLD = ~

E V -

2.22 -

Y - exp(-Aat)

Where:

LLD = the "a priori" lower limit of detection (picoCuries per ur.it mass or volume),

s h = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute).

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volums),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec 1), and l l

" At = the elapsed ti e between sample collection, or end of the sample collection pariJ, and time of counting (sec).

Typical values of E, V, Y, and at should be used in the calculation.

t V0GTLE . UNIT p! 3/4 12-11 APR 34 W

n .. - . -. .

l^

RADIOLOGICAL ENVIRONMENTAL MONITORING .

3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 ALandUsg)Censusghallbeconductedandshallidentifywithina s distance ofederA5 milesA the location irt elch of the 16 meteorological sectorddfthenearestmitkani 1, the_ 8 pearest residence, and the nearest garde # of greater than 40mmiD 00 ftpproducing broyd leaf vegetation.Lgfu/

wiMM -/44 34f4ned kWW /*nt May k kCJsdr# N/M $HJ SUff .

APPLICA8ILITY: At all times. l ACTION:

. a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4. u.2.3, pursuant to Specifica-tion 6.9.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, jf /rj a rf a /4//q f/c

b. With a Land Use Census identifying a ocation(s) that yields a .

calculated dose or dose commitment in the same exposure pathway) 205 greater than at a location from which samples are currently being obtained in accordance with ecification 3.12.1, add the new location (s) within 30 days to the adiological Envi nneental Moni-toring Program given in the 00CM, The sampling location (s), exclud-ing the control station locatio6, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after [0ctober 31] of the year in which this Land Use Census was conducted. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a chartge in the 00CM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s) with informa-tion supporting the change in sampling locations.

~

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l w

V0GTLE - UNIT 1 3/4 M-13

.. Er APR 2 41986

... . ._ . . - - . . -_ . _ _ _ _ - __ -_ = .-

RADIOLOGICAL ENVIRONMENTAL MONITORING / fj. of[,

SURVEIL!.ANCE REQUIREMENTS ,

! 4.12.2 The Land Use Census shall be conducted uring the growing season at l 1 east once per 12 months using that informatio that will provide We-boot good results, such as by a door-to-door survey, ::M:? :;. .;,,-ee by consulting local agriculture authoritie The results of.the Land Use Cen'us s shall be

, included in the Annual Radio ical Environmental Surveillance Report pursuant to 3pecification 6.9.1.3. ,

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RADIOLOGICAL ENVIRONMENTAL MONITORING -

3/4.12.3 INTERLA80RATORY COMPARISON PROGRAM i

LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all regifoactive materials, supplied as part of an Interlaboratory Comparis6n Program that has been approved by the Commission,thatcorrespondtosamples4requiredbyTable3.12-1.

APPLICA8ILITY: At all times. [

ACTION: -

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Comeission in the Annual Radiological Environmental Surveillance Report pursuant to Specification 6.9.1.3.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

_ ._. 5URVEILLANCE REQUIREMENTS ._.

4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Surveillance Report pursuant to Specification 6.9.1.3.

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RADI0 ACTIVE EFFLUENTS BASES _

3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-I tially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen.and oxygen. [ Automatic control features are included in the 4ystem to prevent the hydrogen and oxygen concentrations from reaching these flammability liinits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.] Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4'11.2.6 GAS STORAGE TANKS

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The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification. . Restricting.the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 res.

This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Wasta Gas System Leak or Failure," in NUREG-0800, July 1981. Since only the gamma body dose factor (DFBj )

is used in the analysis, the Xe-133 equivalent is determined from the DFBg value for Xe-133 as compared to the composite DF89 for the actual mixture in the tank.

3/4.11.3 SOLID RADI0 ACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, waste type, waste pH, waste / liquid /SQLIDIFICATION agent / catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

3/4.11.4 TOTAL DOSE 4

ThisspecificationisprovidedtomeetthedoselimitationsofbCFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report when-ever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 areas to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mress. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside V0GTLE - UNIT 1 E B 3/4 11-6 ggg

3/4.12 RATI0 LOGICAL ENVIRONMENTAL MONI'TORING i l

BASES i

3/4.12.1 MONITORING PROGRAM N '"U N #M M OR

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The Radiological Environmental Monitoring Program required by this specification provides representative measuremenu of radiation and of radio-s active materials in those exposure pathways =and for those radionuclides that lead to the highest potential radi'ation exposure of MEleERS OF THE PU8LIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplerents the Radiological Effluent Monitoring Program by :: "yM; '"t t'  ::rch meawinj concentrations of radioactive materials and levels of radiation -- ~ ' t . =

4henexpectedonthebasisoftheaffluentmeasurementsandthemodelIn'gof the environmental s'xposure pathways. Guidance for this monitoring program is provided by the_ Radiological Assetsment Branch Technical Position _ on Environ-mental Monitorina >The initially specified monitoring program will be effective C-Following this period,

//_(f program fiirWeEt the first changes _may 3 beyears initiated of commercial based on operationaloperation.

experience.

The required detection' capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12'-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori'(before the fact) limit representing the capability of a measure-ment system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This' census satisfies the requirements of Section IV.B.3 of Restricting the census to gardens of greater 5000* Appendix tha gn I to 10 CFR Part 50.provides assurance that significant exposure pathwa I m e tables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the  :

garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage). and (2) a vegetation yield of 2 kg/ma, V0GTLE - UNIT ,1 ,=.~ 8 3/4 12-1

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