Text

Forwards Summary Lists of 840503 Changes,Draft Tech Specs & Resolved Items & Summary List of Status & Draft Tech Specs for 840405 Appeal Items.Tech Specs Believed to Accurately Reflect Design & Operating Program Described in FSAR
	ML20084M283
Person / Time
Site:	Callaway
Issue date:	05/11/1984
From:	Schnell D; UNION ELECTRIC CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	ULNRC-816, NUDOCS 8405150296
	Download: ML20084M283 (43)
	v • d • e

,

...- ~. -.

. -. - -. ~. ~,

\\

l t

i UNION ELECTRIC COM PANY

[

1908 ORATIOT STREET.

~ ST. Louis, MISSOURI i

~

mea 4WNG ADDREser

.r. e.:.,:::.'::,.....

~:.. ::~.~v May 11_, 1984 I

f

)

t

Mr.' Harold R. Denton, Director i

Office of Nuclear. Reactor Re<p11ation l

ji U.S. Nuclear Regulatory Commission j

' Washington, D. C. 20555 i

I q

Dear Mr. Denton:

ULNRC-816 1

DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 CALLAWAY TECHNICAL SPECIFICATIONS r

r if

References:

1) D. G. Eisenhut letter to D. F. Schnell j

dated March 8, 1984 i

2) ULMRC-787 dated April 5, 1984 e

3) ULNRC-792 dated April 9, 1984

4) D. G. Eisenhut letter to D. F. Schnell i

dated May 3,-1984 l

Attachments:

1) Summary Listing of those pages transmitted by Reference 4 on which f

UE concurs.

I

2) Specifications resolved subsequent to Reference 4.

I

3) Status of Specifications pursuant to L

Reference 2.

j I

Reference 1 transmitted the Callaway Technical Specifications in l

' final draft form.

Reference 3 transmitted Union Electric Company's

(

i confirmation, with exceptions, that the draft accurately reflected'the j

plant design and operating program as described in the FSAR and other

[

information on our docket.

Reference 2 requested appeals on three i

specifications.

l Reference 4 transmitted numerous changes made to the callaway Technical' Specifications since the issuance of Reference 3.

During i

review of Reference 4, continuing review of all technical i

i; specifications, and in meetings with the staff, Union Electric Company has identified and included'as attachments to this letter those changes ;

necessary to ensure the Callaway Technical Specifications accurately reflect the plant design and operating program.

I is a summary list of changes transmitted by Reference 4 with which Union Electric concurs.

I I!

i

=8405150296 840511' 1

F PDR ADOCK 05000483 g

A

.PDR j

ULNRC-816 Mr. Harold R. Denton Page 2 I

, is a summary list and attached specifications of those items resolved between Union Electric'and the staff subsequent to Reference 4.

is a summary list, status, and attached specifications (as appropriate) for those appeal items identified in Reference 2.

Except as noted herein and in Reference 3, in my judgement, the callaway Technical Specifications accurately reflect the plant design i

and operating program as described in the FSAR and other information on our docket.

Very truly yours, I

Donald F. Schnell DFS/bjk i

Attachments i

cc:

J. J. Holonich t

9 f

STATE OF MISSOURI )

)

SS CITY OF ST. LOUIS )

Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By Donald F. Schnell Vice President i

Nuclear SUBSCRIBED and sworn to before me this

//

day of 198 BARBAR J.'PF F NOTARY PUBUC, STATE OF MISSOURI MY COMMISSION EXPIRES APRIL 22,Iggg SL LOUIS COUNU t

6 D

.. ~.

cc:

Glenn L. Koester Vice President Operations Kansas Gas & Electric P.O. Box 208 Wichita,, Kansas 67201 Donald T. McPhee Vice President Kansas City Power and Light Company 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.

Washington, D.C.

20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 John H. Neisler callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 William Forney Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077

ATTACIBGElft 1 P 331 cf 2 i

I Item Page Agree Open Issue-f s

l' IV -

x Editorial 2

V x

Editorial "3

VI x

Editorial 4

IX x

Removal of Bit Spec t

5 XIV x

Editorial f

6 XV x

Deletion of Bit Spec l

7 XX x

Editorial 4

8 XXI x

Editorial

{

9

.2-7 x

P-10 Setpoint Change 10 B2-2 x

Editorial (RSB)

[

11 B2-6 x

Editorial (RSB) i 12 3/4-1-7 x

Boration System i

13

-3/4 1-8 x

Added Cop Footnote 14 3/4 1-9 x

Editorial (RSB) 15 3/4 1-10 x

Editorial (RSB) f E

16 3/4 1-11 x

Boration System 17 3/4 1-12 x

Boration System l

18 3/4 1-13 x

Boration System

.19 3/4 1-14 x

Editorial

[

20-3/4 1-18

.x Editorial 21

-3/4 1-20 x

Editorial 22 3/4 1-21 x

Editorial

-23' 3/4 2-8 x

Flow Uncertainties 4

j, 24 3/4 2-9 x

Flow Uncertainties I

25

'3/4 2-10 x

Flow Uncertainty Surveillance

{

26 3/4 3-2 x

SRM (RSB)

[

27 3/4 3-6 x

SRM Action Statements (RSB) l 0

28 3/4'3-14 x

Change ## to # (RSB) 29 3/4 3-16 x

Added Mode 4 to Item 4.a & b (RSB) i 4'

30 3/4 3-17 x

Delete Mode 3 from Item 5.a Change Action ~

[

31 3/4 3-19 x

Add Solid State Load Sequencer 32 3/4 3-20 x

Deleted Original ## Footnote

[

I 33 3/4 3-21 x

Added Action Statements

}

.34 3/4 3-24 x

Editorial 35 3

Added Sem Line Neg High Rt (RSB) x i',

36 3/4 3-40 a

Change in ### Note i

-37 3/4 3-44 x

Change in Acceleration Level l

38 3/4 3-45 x

change in ACOT 39-3/4 3-52 x

Change in Action Statement 40 3/4 3-53 x

Reg Guide 1.97 Instrumentation l

41 3/4 3-54 x

Reg Guide 1.97 Instrumentation

[

42 3/4 3-55 x

Reg Guide 1.97 Instrumentation 43 3/4 3-56 x

Reg Guide 1.97 Instrumentation

[

44 3/4 3-60 x

Fire Detection Instrumentation

[

45 3/4 3-70 x

Editorial l

46 3/4 3-73 x

Editorial 47 3/4 3-75 Added Note 5 4

f

Subsequenily changed to an Attachment 2 item. See Items 1 and 2 of Attachment 2.

l r

ATTACHMENT I P go 2 cf 2 Item Page Agree Open Issue 48 3/4 4-10 x

Added Footnote 49 3/4 4-15 x

Editorial 50 3/4 4-20 x

Change Valve Nomenclature 51 3/4 4-21 x

Editorial (RSB) 52 3/4 4-29 x

Added Figure 3.4-4 to Surv. (RSB) 53 3/4 4-35 x

RHR Suction Reliefs 54 3/4 5-3 x

Change in Footnote (RSB) 55 3/4 5-8 x

change in Surveillance (RSB) 56 3/4 5-10 x

Bit' Removal 57 3/4 6-2 x

Reduced Pressure Testing 58 3/4 6-3 x

Reduced Pressure Testing 59 3/4 6-5 x

Change 0.1 La to.05 La 60 3/4 6-13 x

Change Surv. Accept. Criteria 61 3/4 6-16 x

Removal of 3.0.4 62 3/4 6-20 x

Editorial 63 3/4 6-29 x

Editorial l

64 3/4 6-30 x

Added Action. Statement 65 3/4 7-28 x

No Change 66 3/4 7-36 x

Editorial 67 3/4 E-1 x

Editorial 68 3/4 8-2 x

Moved Surv.

69 3/4 8-6 x

Editorial i

70 3/4 8-8 x

RHR Suction Relief Issue l

71 3/4 8-10 x

Editorial 72 3/4 8-12 x

RHR Suction Relief Issue 1

73 3/4 8-15 x

Editorial 74 3/4 8-17 x

Ckt Bkr Issue thru 8-46 75 3/4 10-4 x

Editorial 76 3/4 11-6 x

Radwaste 77 3/4 11-9 x

Added Note 78 3/4 11-11 x

Added Note 79 B3/4 1-2 x

Duration System 80 B3/4 1-3 x

RHR Suction Relief 81 B3/4 2-5 x

Flow Uncertainties 82 B3/4 4-1 x

6 Hours (RSB) 83 B3/4 4-2 x

Editorial 84 B3/4 4-3 x

Editorial 85 B3/4 4-4 x

Editorial 86 B3/4 4-15 x

Add Cold Overpressure Cases thru 4-17 87 B3/4 5-1 x

Bit Deletion thru 5-2 88 B3/4 7-2 x

Added St.nt to AFW Bases (RSB) 89 B3/4 10-1 x

Editorial 90 B3/4 6-3 x

Org Chart Management 91 B3/4 6-4 x

r' ATTACHMENT 2 Pigo 1 cf 1 Item Page Agree Open Issue 1

3/4 3-16 x

Deletion of Mode 4 Reqmt. for Item 4 2

3/4 3-26 x

Condensate Storage Tank Level Setpoint 3

3/4 3-35 x

Deletion of Mode 4 Reqmt. for Item 4.e 4

3/4 3-59 x

Fire Detection Instrumentation 5'

3/4 3-72 x

Deletion of ACOT for 3.e 6

3/4 3-73 x

Deletion of ACOT for 4.e 7

3/4 4-2 x

Reqmt. for 2 Operating RCP's for Mode 3 8

3/4 4-10 x

PORV Specification (RSB) 9 3/4 4-34 x

Editorial 10 3/4 5-6 x

SI Pump Flow Rate 11 (deleted) 12 3/4 7-6 x

Condensate Storage Tank Level 13 3/4 7-15 x

containment Ventilation Specification 14 3/A 7-31 x

Fire Detection Flow Tests 15 3/4 8-9 x

Battery Charger (PSB) 16 3/4 8-13, x

Battery Charger (PSB) l 14 l

17 3/4 7-30 x

Fire Suppression System l

t 4

L----

TABLE 3.3-

. Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRLMENTATION S

NINICSM

{

TOTAL NO.

-CHANNELS CHANNELS APPLICABLE 1

c FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE N00ES ACTION E

e 3.

Containment Isolation (continued)

.E 2)

Automatic Actuation 2

1 2

1,2,3,4 17 Logic and Actuation j

Relays (SSPS) i 3)

Automatic Actuation Logic and Actuation i

Relays (80P ESFAS) 2 1

2 1,2,3,4 17 4)

Phase "A" Isolation See Item 3.a. for all Phase "A" Isolation initiating j

functions and requir.ements.

i w

4.

Steam Line Isolation 1

i a.

Manual Initiation w

1) Individual 1/ steam line 1/ steam line 1/ operating 1, 2, 3f/

23 steam line L

2) System 2

1 2

1,2,3 /

h f

El l

b.

Automatic Actuation 2

1 2

1,2,3 f M

f Logic and Actuation Relays (SSPS)

I c.

Containment Pressure-3 2

2 1,2,3 15*

High-2 d.

Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15*

Pressure-Low any steam line ff 15*

e.

Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line 38#

Negative Rate-High any steam-line

=

g LA

TABLE 3.3'-4 (Continued)

{

ENGINEERED SAFETY FEATURES ACTUATION SYSTiM I:4STRUNENTATION TRIP SETPOINTS

.E s

TOTAL SENSOR TRIP ALLOWA8LE

'g FUNCTIONAL UNIT ALLOWANCE (TA)

Z ERROR (S)

SETPOINT VALUE M

6.

Auxiliary Feedwater (Continued)

M e.

Safety Injection-Start Motor-Driven Pumps See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

f.

Loss-of-Of f site Power-Start Turbine-Driven Pump N.A.

N.A.

g.

Trip of All Main M

Feedwater Pumps-Start Motor-Driven

{

Pumps N.A.

N.A.

M.A.

m h.

Auxiliary Feedwater Pump Suction Pressure-21.1 ZO fA

>&4 psa

>ft-79 psa Low (Transfer to ESW)

N.A.

7.

Automatic Switchover to Containment Sump a.

Auto Lic Actuation Logic and Actuation Relays (SSPS)

N.A.

M.A.

N.A.

s.

b.

RWST Level-Low-Low 3.4 1.21 2.0

.>36%

>35.2%

~

Coincident with Safety Injection See Item 1. above for Safety Injection-Trip-Setpoints -and Allowable Values.

8.

Loss of Power a.

4 kV Undervoltage

-Loss of Voltage N.A.

N.A.

83V (120V Bus) 83+0;-8.3V (120V Bus) w/Is delay w/1+0.2,-0.5s delay

- ~_. - _

I TABLE 4.3-2 (Continued) c.

l 5

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION i

e l

SURVEILLANCE REQUIREMENTS l

l TRIP c

l ANALOG ACTUATING ISOES i

CHANNEL DEVICE MASTER SLAVE FOR teilCN

)

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLAIN j

FtRICTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS RE0utRis 4.

Steam Line Isolation s

a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,'2, 3 l

b.

Automatic AcLuation N.A.

N.A.

M(1)

Q 1,2 3 v

l Logic and Actuation i

j Relays (SSPS)

{

c.. Containment Pressure-S R

M N.A.

N.A.

1, 2, 3 w

L

)

Nigh-2 l

Y d.

Steam Line Pressure-S R

M N.A.

N.A.

1, 2, 3 i

U Low l

3/

e.

Steam Line Pressure-S R

M N.A.

N.A.

7 Negative i

Rate-Nigh 5.

Feedwater Isolation & Turbine Trip 1

a.

Automatic Actuation M.A.

N.A.

M(1)

Q(3 1, 2 l

Logic and Actuation Relay i

i b.

Steam Generator Water S

R M

N.A.

N. A.4 1, 2-ll Level-Nigh-Nigh i

j c.

Safety Injection See Iteq 1. above for all Safety Injection Surveillance Requirements.

6.

Auxiliary Feedwater a.

Manual Initiation M.A.

N.A.

R' N.A.

N.A.

1,2,3 b.

Automatic Actuation M.A.

M.A.

N.A.

M.A.

M(1)

Q l', 2, 3 Logic and Actuation

{ ^ -

j Relays (SSPS)

TABLE 3.3-11 (C9ntinued)

FIRE DETECTION INSTRUMENTS

[

TOTAL NUMBER OF INSTRUMENTS

i INSTRUMENT LOCATION

[

ZONE HEAT FLAME SM0KE (x/y)

(x/y)

(x/y) i 1406-Comp. Cool. Pop. & Ht. Exch. A.

104 0/1 1406 Comp. Cool. Pop. & Ht. Exch. A 118 2/0 1408-Aux. B1dg. 2026' Cerridor #2 104 0/9 1408-Aux. 81dg. 2026' Corridor #2 118 5/0(1) 1409-Elec. Pene. Rs. 8 106 0/4(1) 1409-Eler. Pene. Rm. 8 113 0/4 I1) l 1410-Elec. Pene. Rs. A 107 0/851) 1410-Elec. Pene. Rs. A 114 0/8

[

1413-Aux. Shutdown Pnl. Re.

118 4/0 l

1501-Ctr1. Rm. A/C & Filt. Units 8.

110 10/0 1504-Ctat. Purge Exh. & Mech. Equip. 8 108 18/0

(

1506-Ctat. Purge Sup. AHU Re. A 109 M/0 L

150 -Personnel Hatch Area 108 3/G t

l 15 Main Steam Iso. Valve Rm. #2 115 1/6 1508-Main Steam Iso. Valve Rs. #1 115 1/6 r

1512-Ctr1. Rs. A/C & Filt. Units A 110 10/0 lb13-Ctri. Bldg. Vent Sup. A/C Unit Rs.

109 3/0' l

Aux Bldg. Duct 2047'6" 119 1/0 1/0((2)

Containment **

201 2/0(2) j Containment **

202 1/0(2)

Containment **

203 2)

Containment **

204 1/0 t

Containment **

206 3/0(2)

Containment **

215 1/0(2)

Containment **

216 1/0(2)

Containment **

217 1/0(2)

Containment **

218 1/0(2)

[

Containment **

219 4/0 l

Containment **

220 1/0(2) j 3101-Ctr1. 81dg. 1974' Pipe Space 300 11/0 l

3105-Ctr1. Bldg. Elec. Chase S. 1974' 300 1/0 3106-Ctri. Bldg. Elec. Chase N. 1974' 300 1/0

-Area Above Access Control 301 12/0

(

3229-Ctr1. 81dg. Elec. Chase S. 1984' 300 1/0 t

i 3230-Ctr1. 81dg. Elec. Chase N. 1984' 300 1/0 3301-ESF Swgr. Rm. #1 314 0/7 l

3301-ESF Swgr. Rm. #1 315 0/7(g) i 3302-ESF Swgr. P.m. #2 316 0/5 3302-ESF Swgr. Rs. #2 317 0/5(1)

)

3305-Ctri. Bldg. Elec. Chase S. 2000' 301 1/0 l

3306-Ctri. Bldg. Elec. Chase N. 2000' 301 1/0 l

l 3403-Non-Vit. Swgr. & Xfmr. Rm. #1 304 0/1(1) l 3403-Non-Vit. Swgr. & Xfar. Rm. #1 305 0/1(1) 0/2((1) 3404-Switchboard Rm. #4 321 I

4 1) i 3404-Switchboard Rm. #4 322 0/2

~

3405-8attery Re. #4 303 2/0 l

3407-Battery Rs. #1 303

, 2/0 CALLAWAY - UNIT 1 3/4 3-59 I

I i

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

TA8LE 4.3-9 Q

{

RADIOACTIVE GASEOUS EFFLUENT MDNITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS t

4 ANALOG CHANNEL MDOES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE e

i 5

INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED l

WASTE GAS HOLDUP SYSTEM Explosive 1.

Gas Monitoring System a.

Inlet Hydrogen Monitor.

D N.A.

Q(4)

M b.

Outlet Hydrogen Monitor D

N.A.

Q(4)

M c.

Inlet Oxygen Monitor D

N.A.

Q(5)

M d.

Outlet Oxygen Monitor D

N.A.

Q(6)

M u

1 2.

Unit Vent System l

'f a.

Noble Gas Activity Monitor D

M R(3)

Q(2)

M Providing Alarm (GT-RE-21) b.

Iodine Sampier W

N.A.

l c.

Particulate Sampler W

N.A.

j d.

Flow Rate Monitor D

N.A.

R(7)

Q l

e.

Sampler Flow Rate Monitor D

N.A.

R Q

3.

Containment Purge System l

a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic I

Termination of Release D

P R(3)

Q(1)

(GT-EE-22, GT-RE-33) b.

Iodine Sampler W

N.A.

M.A.

_3 c.

Particulate Sampler W

N.A.

M.A.

N.A.

d.

Flow Rate N.A.

N.A.

R(7)

N.A.

e.

Sampler Flow Rate Monitor D

N.A.

R

+

N.A.

~

TABLE 4.3-9 (Continued) n>

{

RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRFMENTS 5

ANALOG

,a CHANNEL MODES FOR %A11CH e

CHANNEL

. SOURCE CHANNEL OPERATIONAL SURVEILLANCE 6

INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIREO i.

4.

Radwaste Building Vent System t

a.

Noble Gas Activity Monitor -

D. P MP R(3)

Q(1)

Providing Alarm and Automatic Teral6ation of Release (GH-RE-10) b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W

N.A.

j i

d.

Flow Rate N.A.

N.A.

R(7)

N. A'.

1 u

.'a e.

Sampler Flow Rate Monitor D

N.A.

R

+

i N.A.

1 1

1 4

I l

i 4

t J.

~ _ _

REACTOR COOLANT SYSTEM HOT STAN08Y LIMITING CONDITION FOR OPERATION

' three, 1

3.4.1.2 At least 4wo-of the reactor coolant loops listed below shall be OPERABLE and at least one-of these reactor coolant loops shall be in operation:"

two i

a.

Reactor Coolant loop A and its associated steam generator and reactor coolant pump, b.

Reactor Coolant Loop B and its associated steam generator and reactor coolant pump, c.

Reactor Coolant Loop C and its associated steam generator and reactor coolant pump, and I

d.

Reactor Coolant Loop D and its associated steam generator and reactor coolant pump.

APPLICABILITY: MODE 3.

ACTION:

a.

With less than the above required reactor coolant loops OPERABLE,

(

restore the required loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

SEr. Nsen:r c 4r With no reactor coolant locp in operation, suspend all operations involving a reduction in baron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant loop to operation.

l SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE ance per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 The required steam generators shall be determined OPERABLE by l

verifying secondary side wide range water level to be greater than or equal to 10% at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2.3 At least N reactor coolant loop.!shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l "All reactor coolant pumps may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

(1) no operations are permitted that would cause dilution of the Reactor l

Coolant System baron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

l I

l l

CALLAWAY - UNIT 1 3/4 4-2 i

~ _ -.

Insert for Specification 3.4.2.2 Action b.

With only one reactor coolant loop in operation, restore at least two reactor coolant loops to operation in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All ' power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.*

ACTION:

N tw With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either rest s

PORV(s) to OPERABLE status or close the associated bl valve (s) and ove power from the block valve (s); otherwise n at least HOT STA within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD

' DOWN within the following 30 s.

SEE b.

With one or more block ve(s) parable, within 1 hour:

restore IMSERT the block valve (s) to OPER status, or close the block valve (s) and remove power fro block ve(s), or close the PORV and remove power fr s associated sole d valve; otherwise, be in at least HOT BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in COLD SHUTDOWN withi e following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The provisions of Specification 3.0.4 are not applicabl.

SURVEILLA'NCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION.

l 1

4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION,a: in Specification 3.4.4.

h 0P h i

With all RCS cold leg temperatures above 368'F.

1 l

i i

CALLAWAY - UNIT 1 3/4 4-10

-,,--,,--g

,-,--,-----w----am,

w

---.---------,,---->--m-

Inscre for Sp:cificatica 3.4.4 ACTION:

With one or more PORV(s) inoperable because of excessive seat a.

leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the FORV(s) to OPERABLE status or close the associated block valve (s); otherwise be in at least BOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD $5UTDOWN

[

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

l

~

b.

With one FORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the FORY to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORY to OPERABLE status within f

the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next j

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l c.

With both PORV(s) inoperable due to causes other than excessive i

seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore each of the PORV(s) to OPERABLE status or close their associated block valve (s) and remove power from the block valve (s) and be in HOT STANDBY within r

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With one or more block valve (s) inoperable, within 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

)

1) restore the block valve (s) to OPERABLE status, or close the

{

block valve (s) and remove power from the block valve (s), or close the PORY and remove power from its associated solenoid valve; and 2) apply the' ACTION of b or c above, as appropriate for the isolated PORV(s).

t The provisions of Specification 3.0.4 are not applicable.

i e.

I l

i I

i i

?

i i

J l

l

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Prot:betion Systems shall be OPERA 8LE:

a.

Two residual heat removal (RHR) suction relief valves each with a Setpoint of 450 psig i 1%, or b.

Two power-operated relief valves (PORVs) with Setpoints which do not exceed the limit established in Figure 3.4-4, or c.

The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2 square inches.

APPLICABILITY:

MODE 3 when the tamperature of any RCS cold' leg is less than or equal to 368'F, MODES 4 an:: 5, and MODE 6 with the reactor vessel head on.

ACTION:

a.

With one PORV and one RHR suction relief valve inoperable, either restore two PORVs or two RHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and I

b.

With both PORVs oe both RHR suction relief valves inoperable, I

depressurize and venc the RCS through at least a 2 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

In the event the PORVs, or the RHR suction relief valves, or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence, l d.

The provisions of Specification 3.0.4 are not applicable.

CALLAWAY

, UNIT 1 3/4 4-34

~

EMERGENCY CORE COOLING SYSTEMS I

SURVEILLANCE REOUIREMENTS (Continued) h.

By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:

1)

For centrifugal charging pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 346 gpm, and b)

The total pump flow rate is less than or equal to 550 gpm.

2)

For Safety Injection pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 462 gpm,'

and 655 b)

The total pump flow rate is less than or equal to i59 gpm.

i.

.By performing a flow test, during shutdown, following completion of modifications'to the RHR subsystems that alter the subsystem flow characteristics and verifying that for RHR pump lines, with a single pump running:

1)

The sum of the injection line flow rates is greater than or equal to 3800 gpm, and 2)

The total pump flow rate is less than or equal to 5500 gpm.

CALLAWAY -, UNIT 1 3/4 5-6

l PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be OPERABLE with a contained water volume of at least-212,700 gallons.

E91,ooo APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

With the CST inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a.

Restore the CST to OPERABLE status or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or b.

Demonstrate the OPERABILITY of the Essential Service Water (ESW)

System as a backup sup11y to the auxiliary feedwater pumps and restore the CST to OPERABLE status'within 7 days or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water volume is within its limits when the tank is the supply source for the auxiliary feedwater pumps.

4.7.1.3.2 The ESW System shall be demonstrated CPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the ESW System is in operation whenever the ESW System is the supply source for the auxiliary feedwater pumps.

CALLAWAY - UNIT 1 3/4 7-6

)

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.

At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by,:

1)

Verifying that the Control Room Emergency Ventilation System satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a. C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm + 10% for the Filtration System and

~

2000 cfm i 10% for the Pressurization System with 500 cfm i 10%

going through the Pressurization System filter adsorber unit; 2)

Verifying, within 31 days after removal, that a laboratory analysis l

of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, 1

March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and 3)

Verifying a system flow rate of 2000 cfm + 10% for the Filtration System and 2000 cfm i 10% for the Pressurization System with 500 cfm i 10% going through'the Pressurization System filter adsorber unit during system operation when tested in accordance l

with ANSI N510-1975.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal, that a laboratory analysis of a represen-t tative carbon sample obtained in accordance with Regulatory Position l

C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the t

laboratory testing criteria of Regulatory Position C.6.a of Regulatory j

Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

i e.

At least once per 18 months by:

1)

Verifying that the pressure drop across.the combined HEPA filters and charcoal adsorber banks is less tnan 5.4 inches

(

Water Gauge while operating the system at a flow rate of 1

i 2000 cfm 210% for the Filtration System and 500 cfm i 10% for the Pressurization System filter adsorber unit; 2)

VerifyingthatonaControlRoomVentilationIsolationtestsigna(,.

l the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber l

banks; Verifying that the system maintains the control _ room at a positive pressure of greater than or equal to M inch Water b 3)

Gauge et less thea er equal te a pres:uri:etier '10:r cf 400 ef-l relative to,:dj::ent :reas-during system operation; and the cuts #do aimesphere, 4)

Verifying that the Pressurization System filter adsorber unit heaters dissipate 15 1 2 kW in the Pressurization System when tested in accordance with ANSI N510-1975.

l CALLAWAY, UNIT 1 3/4 7-15

PLANT SYSTEMS SPRAY AN0/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.10.2 The following Spray and/or Sprinkler Systems shall be OPERABLE:

a.

Wet Pipe Sprinkler Systems Buildina Elevation Area Protected Auxiliary 2000/2020, North Electric Cable Chase Auxiliary 1988/2000/2o2/, South Electric Cable Chase Control 1974 - 2073 Vertical Electrical Chases Control 1974 Pipe Space and Tank Room Control 1992 Cable Area Above Access Control b.

Pre-Action Sprinkler Systems Buildina Elevation Area Protected Auxiliary 1974 Cable Trays

Auxiliary 2000 Cable Trays

Auxiliary 2026 Cable Trays

Control 2032 Lower Cable Spreading Room Control 2073 Upper Cable Penetration Area Reactor 2026 North Cable Penetration Area Reactor 2026 South Cable Penetration Area Diesel Gen. (E) 2000 East Diesel Generator Room Diesel Gen. (W) 2000 West Diesel Generator Room c.

Water Sprays Systems Buildina Elevation Area Protected Auxiliary 2000 Auxiliary Feedwater Pump Turbine ESF Transformer Grade Transformer XNB01*

ESF Transformer Grade Transformer XNB02*

APPLICABILITY: Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.

ACTION:

a.

With one or more of the above required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Areas contain redundant systems or components which could be damaged.

CALLAWAY - UNIT 1 3/4 7-30

PLANT SYSTEMS l

SURVEILLANCE REQUIREMENTS t

4.7.10.2 Each of the above required Spray and/or Sprinkler Systems shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct position; b.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel; c.

At least once per 18 months:

1)

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct positions on a Simulated Fire test signal, and b)

Cycling each valve in the flow path that is not testable during plant uperation through at least one complete cycle of fullttravel." 1.

l

2) 2By a visual inspection. of' the dry pipe spray. and sprinkler t er headerstto verify their integrity,i end 0-l

3) 1By a. visual inspection bfs each nozzle's' spray, area toi varify the t;,

i spray 1 pattern is!not obstructed.t-er Ator' d.

d At least once. per :3 year,s: by, performing' an: ai flow test..throughu each. open head. spray / sprinkler header:and verifying each open head

+

spray / sprinkler hozzle ds unobstructed.e :

l i.

CALLAWAY V UM1 TT 1 3/4 7-3r u i

' ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING t

LINITING CONDITION FOR OPERATION l

i 3.8.2.1 As a minimum, the fe11owing D.C. electrical sources shall be OPERA 8LE:

i a.

125-Volt Battery Bank NK11 and NK13, and its associated Full Capacity Chargers NK21 and NK23, or b.

125-Volt Battery Bank NK12 and NK14, and its associated Full capacity l

Chargers NK22 and NK24.

APPLICA81LITY: MODES 1, 2, 3, and 4.

l i

ACTION:

or ds assousted chargv With one of the required cattery banks ^ inoperable, restore the increrable hat 9.ory bank.to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at ' east HO" 5"AN08Y within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and in COLD SHUTDOWN g a g a w ch,,9,within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

5.

M 'l x : Of " 7:; ird fell :- rity f:,;r; ix;:r;tle, i-xtr:t:

"; 0"C.."?ILIT" ;1' it; n;;-i;t-d bett;;j tri ti ;;.-f;--.;; ^f

' rift::ti:- 4.S.2.10.1) d thir. 1 t xr, xd t t r:t x x ; r S t r :

' % r,:^ft:r.

If x, C,;t,;.i A i kit 17. T:51: ?.S

i: ;t s t,

>_____m.

um__.

______ms SURVEILLANCE REQUIREMENTS 4.8.2.1 Each 125-volt battery bank and charger shall be demonstrated OPERA 8LE:

a.

At least once per 7 days by verifying that:

1)

The parameters in Table 4.8-2 seet the Category A limits, and 2)

The total battery terminal voltage is greater than or equal to 134 volts on float charge.

I 1

l CALLAWAY - UNIT 1 3/4 8-9 a

ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION OPERATING LIMITING CONDITION FOR OPERATION 3.2.3.1 The following electrical busses shall be energized in the specified manner with tie breakers open between redundant busses within the unit:

a.

Division #1 A.C. Emergency Busses consisting of:

1) 4160-Volt Emergency Bus #N801, and 2) 480-Volt Emergency Busses #NG01, NG03 and NG05E.

b.

Division #2 A.C. Emergency Busses consisting of:

1) 4160-Volt Emergency Bus #N802, and 2) 480-Volt Emergency Busses #NG02, NG04 and NG06E.

c.

120-Volt A.C. Vital Bus #NN01 energized from its associated inverter connected to D.C. Bus #NK01, d.

120-Volt A.C. Vital Bus #NN02 energized from its associated inverter connected to D.C. Bus #NK02, e.

120-Volt A.C. Vital Bus #NNO3 energized from its associated inverter connected to D.C.. Bus #NK03, f.

120-Volt A.C. Vital Bus #NN04 energized from its associated inverter connected to D.C. Bus #NK04, g.

125-Volt D.C. Bus #NK01 energized from Battery #NK11 and Charger #NK21 NN h.

125-Volt D.C. Bus #NK02 energized from Battery #NK12 and Charger #32, NM i.

125-VoltD.C. Bus #NK03energizedfromBattery#NK13andCharger[23, and NK

^

j.

125-Volt D.C. Bus #NK04 energized from Battery #NK14 and Charger #24.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With one of the required divisions of A.C. emergency busses not fully energized, reenergize the division within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With one A.C. Vital bus either not energized from its associated inverter, or with the inverter not connected to its associated D.C.

bus:

(1) reenergize the A.C. Vital bus within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , and (2) reener0ize the A.C. vital bus from its associated inverter connected to its associated D.C. bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

CALLAWAY - UNIT 1 3/4 8-13

0 ELECTRICAL POWER SYSTEMS LIMITING CON 0!T!0N FOR OPERATION i

ACTION (Continued)

With on'e O.C. bus not energized from its associated battery bank or c.

charger, reenergize the O.C. bus from its associated battery bank and charger within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STAN00Y within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVE!LLANCE REQUIREMENTS 4.8.3.1 The specified busses shall be determined energized in the required manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses, i

i l

I I

g 3/4 4 14 I

CALLAWAY - pNIT 1

\\

i

ATTACletENT 3 Pago i cf 1 Item Page Agree Open Issue 1

3/4 6-8 x

Structural Integrity thru 6-10 1

2 3/4 6-18 x

Provisions of 3.0.4 thru 6-29 l

)

l

l Status of Appeal Items l

l Containment Vessel Structural Integrity (Spec. 3/4 6.1-6,[

SNUPPS presented its appeal to the staff on April 27, 1984. Although we have not received formal notification of the results, we were informed by Mr. Tom Novak via telecon on 5-4-84 that we would be issued Specifi-l cation 3.6.1.6 Attachment 3.

We further understand that this specification is to be tha subject of CRCR review in the reasonably near future. Aside from possible participation in the CRGR review process, we consider this item resolved.

l Overpressure Protection Systems (use of RHR suction relief valves - Spoc. 3/4 4.9.3 This issue was resolved during meetings between the SNUPPS utilities and i

the Reactor Systems B64nch.

Containment Isolation Valves (exemption of the provisions of 3.0.4 - Spec. 3/4 6.3)_

We were informed by the staff that the change we requested was subject to CRGR review before it could be issued, but that exemption from the l

provisions of Spec. 3.0.4 could be granted on a valve-by-valve basis.

This issue was resolved during a telecon between UF and the staff =on I

hay 9, 1984. We have dropped the appeal and have submitted marked up i

specifications in Attachment 3.

It is our belief that our original proposed specification of fers less potential operating restrictions while maintaining an equivalent margin of safety and therefore should be presented to the CRGR for review.

l i

i l

l

CONTAINMENT SYSTEMS C0h'iAINMENT VESSEL STRU'CTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

r APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With more than one tendon with an observed lift.off force between the predicted lower limit and 90% of the predicted lower limit or with one tendon below 90% of the predicted lower limit, restore the tendon (s) to the required level of integrity within 15 days and perform an engineering evaluation of the containment and provide a Special Report to the Commission within 30 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With any abnormal degradation of. the structural integrity other than ACTION a. at a level below the acceptance criteria of Specifica-tion 4.6.1.6, restore the containment vessel to the required level of integrity within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and perform an engineering evaluation of the containment and provide a Special Report to the Commission within 15 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Vessel Tendons.

The containment vessel tendons' struc-tural integrity shall be demonstrated at the end of 1, 3, and 5 years following the initial containment vessel structural integrity test and at 5 year intervals thereafter.

The tendons' structural integrity shall be demonstrated by:

a.

Determining that a random but representative sample of at least 11 tendons (4 inverted U and 7 hoop) each have an observed lift-off force within predicted limits for each..For each subsequent inspec-tion one tendon from each group may be kept unchanged to develop a

~

history and to correlate the observed data.

If the observed lift off force of any one tendon in the original sample population lies between the predicted lower limit and 90% of the predicted lower limit, two ten' dons, one on each side of this tendon should be checked for their lift-off forces.

If both of these adjacent tendons are found to be within their predicted limits, all three tendons should be restored to the required, level of integrity.

This single deficiency may be considered unique anc~ acceptable.

Unless there is abnormal degradation of the containment vessel during the first three inspec-tions, the sample population for subsequent inspections shall include at least 6 tendons (3 inverted,U and 3*noop);

CALLAWAY - UNIT l' 3/4 6-8 e

b

CONTAIN*1ENTSYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Performing tendon detensioning, inspections, and material tests on a previously stressed tendon from each group (inverted U and hoop).

A randomly selected tendon from each group shall be completely detensioned in order to identify broken-or damaged wires and deter-mining that over the entire length of the removed wire that:

1)

The tJndon wires are free of corrosion, cracks, and damage, 2)

There are no changes in the presence or physical appearance of the sheathing filler grease, and 3)

A minimum tensile strength of 240,000 psi (guaranteed ultimate strength of the tendon material) exists for at least three wire samples (one from each end and one at mid-length) cut from each removed wire.

Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment vessel structure.

c.

Performing tendon retensioning of those tendons detensioned for inspection to their observed lift-off force with a tolerance limit of +6%.

During retensioning of these tendons, the changes in load and elongation should be measured simultaneously at a minimum of three approximately equally spaced levels of force between zero and the seating force.

If the elongation corresponding to a specific load differs by more than 5% from that recorded during installation, an investigation should be made to ensure that the difference is not related to wire failures or slip of wires in anchorages; d.

Assuring the observed lift-off stresses adjusted to account for elastic losses exceed the average minimum design value given below:

Inverted U 139 ksi Hoop:

Cylinder 147 ksi Dome 134 ksi Verifying the OPERABILITY of the sheathing filler grease by assuring:

e.

1)

No voids in excess of 5% of the net duct volume, 2)

Minimum grease coverage exists for the different parts of the anchorage'-system, and 3)

The chemical properties of the filler material are within the tolerance limits as specified by the manufacturer.

CALLAWAY

, UNIT 1 3/4 6-9

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.6.2 End Anchoraces and Adjacent Concrete Surfaces.

The structural integrity of the,end anchorages of all tendons inspected pursuant to Specifi-cation 4.6.1.6.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete grack patterns adjacent j

to the end anchorages.

Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment vessel is at its maximum test pressure.

l 4.6.1.6.3 Containment Vessel Surfaces.

The structural integrity of the exposed accessible interior and exterior surfaces of the containment vessel, including the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of these surfaces.

This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in l

appearance or other abnormal degradatitn.

i i

Y l

l l

I h

l l

l CALLAWAY - UNIT 1 3/4 6-10 I.

[

DRAFT TA8LF 3.6-1 l

\\

CONTAIMIENT ISOLATION VALVES MAXIMUM

~

TYPE LEAX ISOLATION TIME PENETRATIONS VALVE NUISER FUNCTION TEST REQUIRED (Seconds) i 1.

Phase "A" Isolation (active)

P-62 M 88 W-8026 PRT Nitrogen C

10 Iso Valve P-62 w # 88 HV-8027 PRT Nitrogen C

10 l

Iso Valve I

P-24 BG HV-8100 Seal Water Return C

10 i

CTNT Iso Valve l

P-24 BG HV-8112 Seal Water Return C

10 CTMT Iso Valve P-23 BG HV-8152 Letdown System CTNT C

10 Iso Valve P-23 BG HV-8160 Letdown Systes CTMT C

10 Iso Valve I

P-25 8L HV-8047, Reactor Makeup Water C

10 CTMT Iso Valve P-21

# EJ HCV-8825 RHR to SI Test Line A

10

[

Iso Valve P-82

.g # EJ HCV-8890A RHR A to SI Pumps Test A

13 l

Line Iso Valve P-27 4 k EJ HCV-88908 RHR B to SI Pumps Test A

13 Line Iso Valve l

?

P-49

K EM HV-8823 SI/ Accumulator Injection A

10

[

Test Line Iso Valve P-48

t EM HV-8824 Safety Injection Pump 8 A

10 Test Line Iso Valve L

.L i

i kW w pm;s,w a spahdon L a 4 an nd onladc-CALLAWAY - UNIT 1 3/4 6-18

EELLt1(Continggg

!INTADeeff ISOLATI0ll VALVE 3 l

MANDue TYPE LEAK I5( LATI0ll TIM i

g VALVE lE N ER M

TEST REQUIRED f,fxonds) 1.

Phase "A" Isolation (active) - (Continued) 7 P-se

$4 Ell W-8043 Boron Injection up-A 10 streme Test Line Iso P-92 4$ EM W-8871 SI Test Line to adST C

10 l

Iso Valve P-87 4# EM W-8881 Safety Injection Pump A

10 i

Test Line Iso Valve j

P-92

(# St W-8964 SI Test Line System C

10 Outside CTNT Iso P-99 GS W-3 Hydrogen Analyzer 8-A,C 5

Inlet Iso P-99 GS W-4 Hydrogen Analyzer 8 A,C 5

l Inlet Iso l

P-99 GS W-5 Hydrogen Analyzer B A,C 5

Inlet Iso P-56 GS W-8 Hydrogen Analyzer B A,C 5

i Ofsch Iso l

P-56 GS W-9 Hydrogen Analyzer B A,C 5

Disch Iso i

P-101 GS HV-12 Hydrogen Analyzer A A,C 5

Inlet Iso P-101 GS HV-13 Hydrogen Analyzer A A,C 5

l Inlet Iso l

i P-101 GS W-14 Hydrogen Analyzer A A,C 5

Inlet Iso P-97 GS W-17 Hydrogen Analyzer A A,C 5

Disch Iso P-97 GS W-18 Hydrogen Analyzer A A,C 5

Disch Iso

% p.e mis..,op spe;& h e 1.M m J af a dis.

l CALLAHAY - UllIT 1 3/4 6-19

f

}

l TABLE 3.6-1 (continued) i CONTAIMENT ISOLATION VA'.VES l

MAXIMUM i

TYPE LEAK ISOLATIO PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 1.

Phase "A" Isolation (active) - (Continued)

P-101'-

G5 HV-31 Sample Line to CTMT A,C 5

{

Atmos Monitor i

\\

P-101 GS HV-32 Sample Line to CTNT AC 5

Atmos Monitor i

P-97 GS HV-33 Hydrogen Sample Return A.C 5

i From PASS i

^

P-97 GS HV-34

Hydrogen Sample Return A,C 5

From PASS i

P-99 GS HV-36 Sample Line to CTMT.

A,C 5

Atmos Monitor i

P-99 :

GS HV-37 Sample Line'to CTMT AC 5

I Atmos Monitor I

P-56 GS HV-38 Sample Return CTMT A,C 5

Atmos Monitor l

P-56 GS HV-39 Sample Return CTNT A,C 5

l Atmos Monitor P-44 HB HV-7126 RCOT Vent Inside CTMT C

10 i

P-26 HB HV-7136 RCOT Pumps Disch Hde C

10 I

outside CTMT Iso I

r P-44 HB HV-7150 RCDT Vent Outside C

10 l

CTMT i

P-26 HB HV-7176 RCOT Pumps Disch Hrd C

10 Inside CTMT Iso i

P-30 KA FV-29 Reactor'81dg Instr Air C

5 i

Supply Outside CTMT Iso P-32 LF FV-95 CTMT Normal Sumps to C

30 Floor Drain Tank Inside CTMT Iso i

CALLAWAY - UNIT 1 3/4 6-20

I 8

TAS'LE 3.5-1 (Continued)

CONTAINMENT ISOLATION VALVES TYPE LEAK -

ISOLATION TIME l P{NETRATIONS VALVE NUPRER FUNCTION TEST REQUIRED (Seconds) l 1.

Phase "A" Isolation (active) - (Continued)

{

P-32 LF FV-96 CTMT Normal Sumps to C

4 l

Floor Orain Tank Outside CTMT Iso o

i P-93

$ $ SJ HV-5 PZR/RCS Liquid Sample C

5 Inner CTMT Iso l

l P-93 M SJ HV-6 PZR/RCS Liquid Sample C

5

[

Quter CTMT Iso P-69

$ W SJ HV-12 PZR Vapor Sample Outer C

5 CTMT Iso

'l P-69 (2 SJ MV-13 PZR Vapor Saar,le Inner C

5 CTMT Iso P-95

( SJ HV-18 Accumula' tor Sample C

5 i

Inner CTMT Iso P-95 4.g SJ HV-19 Accumulator Sample C

5 l

Outer CTMT Iso I

P-93 g g SJ HV-127 PZR/RCS Liquid Sample C

5 i

Outer CTMT Iso P-64 (4 SJ HV-128 PZR/RCS Liquid A,C 5

Sample Inner CTMT Iso P-64 4 4 SJ HV-129 PZR/RCS Liquid A,C 5

Sample Outer CTMT Iso P-64 4 $ SJ HV-130 PZR/RCS Liquid A,C 5

j Sample Outer CTMT Iso i

Valve P-57

( itSJ HV-131 PASS Discharge to A,C 5

RCDT i

P-57

($ SJ HV-132 PASS Discharge to A,C 5

RCDT 2.

Phhse "A" Isolation (passive)"

5 P-58 M EM HV-8888 Accumulator Tank Fill C

-Mrk Line Iso Valve

)

we prov. m ou 9 a.e,$

i 7.0.H att of *st*lhNt

}

"Il y be cpened on en fnteraf ek basis under administrative contral.

t 4

CALLA Ay juNIT 1 1

3/4 6-21

TABLE 3.5-1 (Continued)

CONTAIMMENT ISOLATION VALVES.

MAXIMLM TYPE LEAK ISOLATION" TIME PENETRATIONS VALVE NUMBER FUNCTI0lg TEST REQUIRE 0 (Seconds) 2.

Phase "A" Isolation (passive)* - (Continued) 3o P-16 Mt EN MV-01 CTMT Reci're Sump to CTNT A

-&A:

Spray Pump A Iso P-13 na EN HV-07 CTMT Rectre Sump to CTNT A Spray Pump 8 Iso j

10 P-45 Mt EP HV-8880

.CTMT Nitrogen Supply C

.wA:

Iso Valve 5

i P-65

,** G5 HV-20 Hydrogen Purge Inner C

CTMT Iso i

5 P-65 A$ G5 MV-21 Hydrogen Purge Outer C

CTMT Iso 4

30 P-67 44 KC HV-253 Fire Protection System C

&An

Mdr Outer CTMT Iso I

y 3.

Phase "8" Isolation (active)

~

P-74 EG HV-58 CCW to RCS Iso C

30 i

P-75 EG HV-59 CCW Return From C

30 I

~

RC5 Iso l

P-75 EG HV-60 CCW Return From C

30 RCS Iso i

P-76 EG HV-61 CCW Return From C

30 I

RCS Iso P-76 EG HV-62 CCW Return From C

30 RCS Iso 4

Containment Purge Isolation (active)

V-161

GT HZ-4 CTMT Mini-Purge C

3 Supply Outside CTMT Iso i

V-161

$ GT HZ-5 CTMT Mini-Purge C

3 i

Supply Inside CTMT Iso I

May De opened on an intermittent n %. yw,s.~s of Spu;Pbasjs under administrative control.d y/w e2m 3.M ar CALLAdAY - UNIT 1 3/4 6-22 p

P"kwws of S 'Odim sw+.w,cN icA P~U k P

3

. - _ - _. -._ -__. - -_ -.- - - -u >sM 2i.y so p.M m d l

{

~

TABLE 3.4-1 (Continued)

CONTA! WENT ISOLATION VALVES MAXIMim TYPE LEAK ISOLATION TIME PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 4.

Containment Purge Isolation (active) - (Continued)

V-160 GT HZ-11 CTMT Mint-Purge C

3 Exh Inside CTMT Iso V-160 GT HZ-12 CTMT Mint-Purge C

3 Exh outside CTMT Iso 5.

Containment Purge Isolation (passive) h, V-161 GT HZ-6 CTMT S/D Purge C

Supply Outside s

CTMT Iso lo V-161 GT HI-7 CTMT S/0 Purge C

-N-Ar Supply Inside CTMT Iso 10 i-160 4

GT HZ-8 CTMT S/0 Purge C

ih*.

Exh Inside CTMT Iso IO l

V-160 GT HZ-9 CTMT S/0 Purge C

MrA.

Exh outside CTMT Iso 6.

Remote Hanual I

i P-41 88 HV-8351A RCP A Seal Water C

N.A.

I Supply P-22 83 HV-8351B RCP S Seal Water C

N.A.

Supply P-39 B8 HV-8351C RCP C Seal Water C

N.A.

Supply I

i P-40 88 HV-83510 RCP 0 Seal Water C

N. A.

Supply P-79 BB PV-8702A RCS Hot Leg 1 to RHR A

N.A.

j Pump A Suction l

M N previssem of S bcalio n

%solst<d 6y k ogrovis,m oC Spee;$41m 3.o.4 ut3.0 4 ore u i

aor ypt,c416. pasa,'

\\

a Ass **n d<vieu' CALLAWAY jjNIT 3/4'6-23 l

,w--....e-a,

,-.,,n.,

--.-,,,,.___w_

__,,,.,w,

...,,,_,-m.

m..,,

,---,--,,,-_n,-

l C

s4.%1- ?

TABLE 3.5-1 (Continued)

'u k_

~'

CONTAll0 S T ISOLATION VALVE 5 MAXDEM TYPE LEAK ISOLATION TIM

, PENETRATIONS VALVE NINGER FUNCTION TEST REQUIRED (Seconds) 6.

Remote Manual - (Continued) r P-52 88 PV-87028 RCS Hot Lag 4 to RHR A

N.A.

Pump a Suction 5

I

.yK EJ W-23 PASS Susp Sample CTNT C

era P-15 Iso 5

P-15 gl( t EJ HV-25 PASS Sump Sample CTNT C

-MrA:

Iso f

5 P-14 EJ W-24 PASS Sump Sample CTNT C

urAr Iso

[Ar P-i4 W. #

EJ HV-26 PASS Sump Sample CTNT C

Iso ESWSupply'[o C

N.A.

P-71 EF HV-31 Containment t

Coolers j

I P-28 EF HV-32 ESW Supply To C

N.A.

l Containment Coolers j

P-71 EF nV-33 ESW Supply To C

N.A.

I Containment Coolers l

P-28 EF HV-34 ESW Supply To C

N.A.

Containment Coolers

~

i P-73 EF HV-45 ESW Return From C

N.A.

Containment i

Coolers P-29

'EF HV-46 ESW Return From C

N.A.

~

Containment-Coolers P-73 EF HV-47 ESW Return From C

N.A.

l Containment Coolers Y

r0JiSuks 0& Spee,'0ck on 3.0.th H'c h lf,'ah/e.

?

CALLAldAY - UNIT 1 3/4 6-24 i

l

\\

pf N/35 m

2,..

TABLE 3.6-1 (Continued) i CONTAIWWIT ISOLATION VALVES MANDEM i

t TYPE LEAK ISOLATION TIM PENETRATIONS VALVE NWSER FUNCTION Eg RE0utREn (seconds) 6.

Remote Manual - (Continued)

P-29 EF W-48 ESW Return From C

N.A.

Containment Coolers i

P-73 EF W-49 ESW Return From C

N.A..

l Containment i

Coolers P-29 EF W-50 ESW Raturn From C

N.A.

Containment Coolers 1

1 P-74 EG W-127*

CCW Supply to RCP C

N.A.

P-75

'EG HV-130*

CCW Return from RCP C

N.A.

P-75 EG HV-131*

CCW Return From RCP C

N.A.

P-76 EG HV-132*

CCW Return From RCP C

N.A.

Themal Barriers P-76 EG HV-133*

CCW from RCP Thermal C

N.A.

4 Barrier P-79 EJ HV-8701A RCS Hot Leg 1 to RHR A

N.A.

Pump A Suction P-52 EJ HV-87018 RCS Hot Leg 4 to RHR A

N.A.

Pump B Suction P-82 EJ HV-8809A RHR Pump A Cold Leg A

N.A.

Injection Iso Valve P-27 EJ HV-88098 RHR Pump B Cold Leg A

N.A.

Injection Iso Valve P-15 EJ HV-8811A CTNT Recire Sump to A

N.A.

RHR Pump A Sucion "These valves were assumed to be closed during the accident analysis, and are normally closed but may be opened on 2n intermittent basis under adminstrative control.

CALLAWAY - UNIT 1 3/4 6-25

,f

':~

&ty1f;;'

a:

2

+

TABLE 3.6-1 (Continued) l

~

CONTAll8tEll? ISOLATION VALVES i

MAXIlut TYPE LEAK ISOLATION TIM PEMETRATIONS VALVE IUSER FUNCTION TEST REQUIRED (Seconds) 6.

Remote Manual - (Continued)

P-14 EJ HV-88115 CTNT Recire Sump to A

N.A.

RHR Pump 8 Sucion P-21 EJ HV-8840 RHR Hot Leg Recirc A

N.A.

i Iso Valve P-87 EM HV-8802A*

SI Pump A 01sch Hot A

1.A.

Leg Iso Valve P-48 EM HV-88028" SI Pump 8 Disch Hot A

N.A.

)

Lag Iso Valve P-49 EM HV-8835 SI Pumps Disch to A

N.A.

i Cold Leg Iso Valve F

CTMT Spr~ y Pimp A A

N.A.

P-89 EN HV-6 a

Disch Iso Valve l

P-66 EN HV-12 CTNT Spray Pump 8 A

.N. A.

Discharge Iso Valve 7.

Active for SIS b

f P-80 SG HV-8105 CVCS Charging Line C

P-88 EM HV-8801A Baron Injection to A

N.A.

f RCS Cold Legs l

P-88 EM HV-88018 Baron Injection to A

N.A.

RCS Cold legs l

8.

Hand-Operated and Check Valves l

P-41 88 V-118 RCP A Seal C

N.A.

Water Supply l

P-22 88 V-148 RCP 8 Seal C

N.A.

I Water Supply

{

l P-39 88 V-178 RCP C Seal C

N.A.

I Water Supply i

i P-40 88 V-208 RCP D Seal C

N.A.

l Water Supply i

"These valves were assumed to be closed during the accident analysis and are normally I

closed but any be opened on an intermittent basis under administrative control.

CALLAWAY - UNIT 1 3/4 6-26 l

i

i l

,.&h6E pf I'$'-

'f

- @h.....

7 ny r

~

TABLE 3.5-1 (Continued) 4 C01KAIl8EIT ISOLATION VALVES IWWW884 TYPE LEAK ISOLATION TDE PENETRATIONS val,VE LEASER,

M EllELIRE (Seconds) 8.

Hend-Operated and Check Valves - (Continued)

P-24 BG V-135 ItCP Seal Water Return C

N.A.

P-80 OS 8381 CVCS Charging Line C

N.A.

P-25 8L 8046 Reactor Nakeup Water C

N.A.

Sipply P-78 M V-045 Steam Generator Orain C

N.A.

Line Iso Valve P-78 m V-046 Steam Generator Orain C

N.A.

Line Iso Valve P-53 EC V-083 Refueling Pool Supply C

N.A.

-From Fuel Pool Cleanup P-53 EC V-084 Refueling Pool Supply C

N.A.

From Fuel Pool Cleanup P-54 EC V-087 Refueling Pool C

N.A.

Return to Fuel l

Pool Cooling P-54 EC V-088 Refueling Pool C

M. A.

Return to Fuel Pool Cooling P-55 EC V-095 Refueling Pool C

N.A.

Skimmers To Fuel Pool Cooling Loop P-55 EC V-096 Refueling Pool C

N.A.

Skimmers To Fuel Pool Cooling Loop P-74 EG V-204 CCW Supply to RCP C

N.A.

P-82 EJ 8818A RHR Pump to Cold A

N.A.

Leg 1 Injection A

N.A.

P-82 EJ 88188 RHR Pump to Cold Leg 2 Injection CALLAWAY - UNIT 1 3/4 6-27

R$.f 502":?l'

=l, k-f[.

?

. ;,n TAB E 3.5-I (Continued)

' "Ma CWifAD8Eff ISOLATION VALVES y

[

MAXDSM l

TYPE LEAK ISOLATION TDE l

PENETRATIONS VAI,VE.10 80t PUNCTION TEST REQUIRED (Seconds) 8.

Hend-0perated and Check Valves - (Continued)

P-27 U 8818C RHR Pump to Cold A

N.A.

Leg 3 Injection P-27 EJ 88180 RHR Pump to Cold A

N.A.

Leg 4 Injection P-21 EJ 8841A RHR Pump Disch to A

N.A.

I RCS Hot Leg 2 P-21 EJ 88418 RHR Pump Disch to A

N.A.

RCS Hot Leg 3 P EM V-001 SI Pump Hot Leg 1 A

N.A.

Injection P-87 EM V-002 SI Pup Hot tog 2 A

N.A.

Injection P-48 EM V-003 SI Pump Hot Leg 3 A

N. A. -

Injection l

l P-48 EM V-004 '

SI Pump Hot Leg 4 A

N.A.

l Injection P-58 EM V-006 Accumulator Fill Line C

N.A.

From SI Pumps P-49 EM V-010 SI Pump Disch to Cold A

N.A.

Leg 1 P-49 EM V-020 SI Pump Disch to Cold A

N.A.

Lag 2 P-49 EM V-030 SI Pump Disch to Cold A

N.A.

Leg 3 P-49 EM V-040 SI Pump Disch to Cold A

N.A.

Leg 4 P-88 EM 8815 BIT to RCS Cold Leg A

N.A.

Injection P-89 EN V-013 CTNT Spray Pump A A

N.A.

to CTNT Spray Nozzles CALUMAY - UNIT 1 3/4 6-28 i

e TABLE 3.6-1 CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TIME PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 9.

Other Automatic P-1

- AB-HV-ll Mn. Stm. ISOL.

A 5

P-2

AB-H V-14 Mn. Stm. ISOL.

A 5

P-3

- AB-HV-17 Mn. Stm. ISOL.

A 5

P-4

- AB-HV-20 Mn. Stm. ISOL.

A 5

P-5

- AE-FV-42 Mn. FW ISOL.

A 5

P-6

- AE-FV-39 Mn. FW ISOL.

A 5

P-7,

- AE-FV-40 Mn. FW ISOL.

A 5

P-8

- AE-FV-41 Mn. FW ISOL.

A 5

P-9

- BM-HV-4 SG Blowdn. kSOL.

A 10 P-10

- BM-HV-1 SG Blowdn. ISOL.

A 10 P-ll

- BM-HV-2 SG Blowdn. ISOL.

A 10 P-12

- BM-HV-3 SG Blowdn. ISOL.

A 10 l

l i

l I

L

- The provisions of Specification 3.0.4 are not applicable.

i i

3/4 6-29 i

ML20084M283

Text

Dear Mr. Denton:

References:

Navigation menu

Search