ML20095A022

Application for Amend to License NPF-24,revising Tech Specs 4.6.2 & 4.6.5.6.2 Re Containment Pressure Control Sys. Marked-up Tech Specs Encl

ML20095A022
Person / Time
Site:	Catawba
Issue date:	08/17/1984
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8408210362
Download: ML20095A022 (14)

Text

DUKE POWER GOMPANY P.O. BOX 33189 CIIARLOTTE, N.C. 28242 IIAL H. TUCKEli TELEPHONE a a rarisse (704)373-453:

August 17, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station, Unit 1 Docket No. 50-413 Technical Specifications

Dear Mr. Denton:

This letter contains proposed amendments to the Technical Specifications for Facility Operating License No. NPF-24 for Catawba Unit 1. The attach-ment contains the proposed change and a discussion of the justification and safety analysis. The analyses are included pursuant to 10 CFR 50.91 and it has been concluded that the proposed amendment does not involve significant hazards considerations.

Pursuant to 10 CFR 50.91 (b)(1) the appropriate South Carolina State Official.

is being provided a copy of this amendment request.

Very truly yours, 44 r <

Hal B. Tucker RWO: sib Attachments cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector t

Catawba Nuclear Station l Mr. Robert Guild, Esq. <

Attorney-at-Law i g\ g P.O. Box 12097 \

Charleston, South Carolina 29412 i'

l 8408210342 840g17 hDRADOCM 05000413

PDR

Mr.-Harold R. Denton, Director August 17,'1984 Page 2 cc: Mr. Jesse L. Riley Carolina Environmental Study Group 854' Henley Place Charlotte, North Carolina 28207

' Palmetto Alliance 21356 Devine Street Columbia, South Carolina 29205

'Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health & Environmental Control 2600 Bull Street Columbus, South Carolina 29201 1

Mr.. Harold R. Denton, Director August 17, 1984 Page 3 HAL B. TUCKER, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this revision to the Catawba N0 clear Station Technical Specifications, Appendix A to License No. NPF-24; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

M f s Hal B. Tucker, Vice President Subscribed and sworn to before me this 17th day of August, 1984.

$Lif Notary Public a )

My Commission Expires: ,

September 20, 1984

Attachment 1 Proposed Amendment to Catawba Unit'l Technical Specifications 4.6.2 and 4.6.5.6.2 Concerning-The Containment Pressure Control System

Attachment 1, Page 1 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINME'NT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION

~

3.6.2 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the refueling water storage tank and transferring suction to the containment sump.

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

ACTION: ,

With one Containment Spray System inoperable, restore the inoperable Spray

. System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 />.

! SURVEILLANCE REQUIREMENTS 1

l-4.6.2 Each Containment Spray System 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 that is not locked, sealed, or otherwise secured in position, is in its correct position;

b. By verifying, that on recirculation flow, each pump develops a differential pressure of greater than or equal to 185 psid when tested pursuant to Specification 4.0.5;

c. At least once per 18 months during shutdown, by:

1) Verifying that each automatic valve in the flow path actuates to its correct position on a Phase "B" Isolation test signal,

! and l 2) Verifying that each spray pump starts automatically on a Phase "B" Isolation test signal.

3) Verifying that each spray pump is prevented from starting by the Containment Pressure Control System when the containment '

I atmosphere pressure is3 4aseter than~ or equal to 0.R psid g less .15

& Is allowed h sNd o} grenlw }han er egaal le 0.ySysd )

rela +ive +s L oufside akosfa,-a, (J I

CATAWBA - UNIT 1 3/4 6-18 l

Attachment 1, Page 2 CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) closeS or

4) Verifying that each spray pump discharge valveA is prevented

, from opening by the Containment Pressure Control System when the containment atmosphere pressure is ; m te. than or equal to 0.3 psid, and less

• LS &Is allowed k open dgnrake $n or egue/ N 0*W.j 5). Verifying that each spray pump is automatically deenergized by the Containment Pressure Control System when the containment atmosphere pressure is g gesete , than or equal to 0.3.psid.

Vss '36

d. .At least once per 5 years by performing an air or smoke flow test, through each spray header and verifying '.each spray nozzle is -

unobstructed.

cgkWe. ko 00-oudside aftneaphere 5

O

!L CATAWBA - UNIT 1 3/4 6-19

Attachment 1, Page 3 CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

f. Verifying that the motor-operated valve in the hydrogen skimmer suction line opens automatically and the hydrogen skimmer fans receive a start permissive signal; and

g. Verifying that with the fan off, the an check damper is- closed.

4.6.5.6.2 At least once per 18 months, each Containment Air Return and Hydrogen Skimmer System shall be demonstrated OPERABLE by :r#'y4 ; th:t :::h

-:1 r: tern 'In it prevented 'r:: :t:rting by the Crntinnt " ::: n 0:ntr;;

fyrte: h;n th :: tzi ::nt irt:rn:? ;rere re i ; rester th:n er ern! te 4.2 prid rel:tiv t: th: cutride at ::;;here. '

a. , Yer *kyin hb CAch air rekurn fan iS deener yreVen4e Oom sbrfInf by be $cn$ai^*en$ fre"'

' 6*"I'*I glee / or

1. Y *I'*'

when +he can4ainmenf interna [gressure is less San or ega<l fo 0 25 psid ornd. is allowed ]c shar) ah feaker ba.nor ef Y h 0 45 sid f , celaktve b &e ca} side b ere j etnd afmo.sp bo Yerihyin$ 4Nah enb dir rekurn' bn isolahan damfer e/ose.s o

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f r* Vin I' A cfening b &e ton $ninmenf fressure Gnfr.( S s}em ONn 3 f* O'2S he cen-luinmenf interna lfressure is ler.s }/la '

f sid and is a({cwed k ofena f t e a ]e r g a ,} oc

'[ "" 0 W fsid, cela}ye fa gz ca}sicle olmesf bere, i

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CATAWBA - UNIT 1 3/4 6-al

Attachment 1, Page 4 JUSTIFICATION AND ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATION The proposed amendments would change the allowable value for the Containment Pressure Control System (CPCS) to prevent the containment spray pumps, the spray pump discharge valves, the Containment Air Return and Hydrogen Skimmer System air return fans and the air return fan isolation dampers from operating at or above 0.3 psid to at or below 0.25 psid. The amendment would also add an allowab?e value for the CPCS to assure allowing operation of the spray pumps, spray pump discharge valves, air return fans and air return fan isolation dampers at or above 0.45 psid. The air return fan isolation dampers need to be added to the Surveillance Requirements since they also receive a direct CPCS signal. The additional changes to the pressure setpoints reflect Allowable Values beyond the Trip Setpoint as allowed in Table 3.3-4 Items 7.a and 7.b.

The safety significance of the setpoints is twofold: (1) The CPCS must terminate or prevent operation of Containment Spray (NS) and Contain-ment Air Return (VX) Systems at or below 0.25 psid to avoid exceeding the minimum containment pressure, and (2) The CPCS must provide start permissives to allow NS and VX actuation at or above 0.45 psid. Both of these Allowable Values are currently contained in Technical Specification Table 3.3-4 items 7.a and 7.b. The values in this table are correct and should be specified in Technical Specifications 4.6.2 and 4.6.5.6.2. These values are within safety analysis limits. The current Surveillance require-ment is in error in that it calls for the CPCS to block NS and VX at or above 0.3 psid instead of at or below 0.3 psid. The Surveillance should assure that the CPCS is blocking NS and VX at or below 0.25 psid.

10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.

The proposed amendment does not increase the probability or consequences of an accident previously evaluated and it does not create the possi-bility of a new or different kind of accident.

The proposed acceptance criteria do not involve a significant reduction in a margin of safety in that the proposed changes are already specified as such per Technical Specification Table 3.3-4, items 7.a and 7.b.

e The Commission has provided guidance concerning the application of standards of no significant hazard determination by providing certain examples (48 FR 14870). One of the examples of actions likely to involve no significant hazards consideration relates to a change which either

Attachment 1, Page 5 may result in some increase to the probability or consequences of a previously-analysed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan. Because the results of the changes are clearly within the applicable acceptance criteria, the example described above can be applie_d to this situation.

For the reasons described above, Duke Power Company concludes that the proposed amendments do not involve significant hazards considerations.

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Attachment 2 Proposed Amendments to Catawba Unit 1 Technical Specifications Concerning Administrative and Typographical Errors

, 'D D -

., TABLE 3.3-4 (Continued) 9 #

i g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E

SENSOR

{

, TOTAL ERROR g FUNCTIONAL UNIT ALLOWANCE (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE

q g 8. Auxiliary Feedwater (Continued) . .

_ fg \ f' jg3

c. Steam Generator Water 19 IF )

Level - Low-Low - ~ -- '

[\ -tih48 ) 1.5

> 17% of span [1  % of Trom 0% to span from 0% to i

i 30% RTP 30% RTP increasing s increasing linearly to

! linearly to 2 53.2% of span

> 54.9% of from 30% to 100%

f

' span from 30% RTP i to 100% RTP

{ d. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable' Values.

e. Loss of-Offsite Power N.A. N.A. N.A.

4 g 1 3500 V t 3200 V

f. Trip of All Main Feedwater 4

Pumps N.A. N.A. N.A.

N.A. N.A.

, g. Auxiliary Feedwater Suction  :

3 s

Pressure-tow 4

i 1) 1 CAPS 5220, 5221, 5222 N.A. N.A. N.A. 1 10.5 psig > 9.5 psig 1 >

', 2) 1 CAPS 5230, 5231, 5232 R N.A. N.A. N.A. > 10.9 psig 1 9.9 psig 8 i *

9. Containment Sump Recirculation 0

,' a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

and Actuation Relays P

y

b. Refueling Water Storage N.A. N.A. N.A.

! Tank Level-Low > 177.15 inches 1 162.4 inches

~

l Coincident With Safety i , Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

i I

TABLE 3.3-6 i h RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS E

S i

. MINIMUM c- CHANNELS CHANNELS APPLICABLE ALARM / TRIP 5

s FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION

• 1.

Containment l

! a. Containment Atmosphere - High 1 1 All *** 30

, Gaseous Radioactivity (Low l Range - EMF-39)

! b. Reactor Coolant System Leakage

{ Detection

1) Particulate Radioactivity i w (Low Range - EMF-38) N.A. I 1, 2, 3, 4 N.A. 33 s

2) Gaseous Radioactivity l Y (Low Range - EMF-39) N.A. 1 1,2,3,4 N.A. 33 E-

{ 2. Fuel Storage Pool Areas

a. High Gaseous Radioactivity -

(Low Range - EMF-42) 1 1 ** -

5 1.7x10 4 pC1/mi 34

b. Criticality-Radiation Level (Fuel Bridge - Low Range -

)

EMF-15) 1 . 1 *

$ 15 mR/h 32 R 1 3. Control Room h

o

Air Intake-Radiation Level - 1/ intake ' 2/M L All $ 1.7x10 4 pCi/ml 31 k

, liigh Gaseous Radioactivity ~,

j (Low Range - EMF-43 A & B) N-1 6 8 m m

l 4. Auxiliary Building Ventilation 1 1 All $ 1.7x10 4 pCi/mi 35 $

j liigh Gaseous Radioactivity -

y

} (Low Range - EMF-41) i .

5.' "omponent Cooling Water System '

IMF-46 A&B) 1 i 1x10 8 pCi/mi 1 All

$3 -

Attachment 2, Page 3 ELECTRICAL POWER SYSTEMS l SURVEILLANCE REOUIREMENTS (Continued) h.

At least once per 10 years or after any modifications whi:h could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 441 rpm in less than or equal to 11 seconds; and

1. At least once per 10 years by:

1) Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or its equivalent, and

2) Performing a pressure test of those. portions of the diesel feel oil system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110% of the system design pressure.

4. 8.1.1. 3 Reports - All diesel generator failures, valid or non-valid, shall be reported within 30 in a Special Report to the Commission pursuant to Specification 6.9.2 days. Reports of diesel generator failures shall include the informa-sion 1, August 1977.in Regulatory Position C.3.b of Regulatory Guide 1.108, Revi-tion recommended a per nuclear unit basis) If the is number greater than of failures in the or equal last to 7, the100 valid report shall tests be(on C supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

4. 8.1.1. 4

Diesel Generator Batteries - Each diesel generator 125-volt battery bank and charger snall ce oemonstrated OPERABLE

a. At least once per 7 days by verifying that:

1) The electrolyte level of each battery is at or above the low mark and at or gN M loQthe high mark,

2) The overall battery voltage is greater than or equal to 125 volts on float charge, and

3) The individual cell voltage is greater than or equal to 1.36 volts on float charge.*

b.

At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110 volts, or battery overcharge with battery terminal voltage above 150 volts, by verifying that:

1) There is noand visible corrosion at either terminals or connectors, "Two oifferent cells shall be tested each month.

CATAWBA - UNIT 1 3/4 8-7

.,r - - - , - . - - - - - - ~ - - - - - - - - - - - , - - - - - . - , , . = - - - - - - - - - - - , - - - - - - ~ - - - , - - - - - - , - - .

Attachment 2, Page 4 ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATION Because the proposed amendments involve only administrative or typographical changes, they do not involve significant hazards considerations according to the standards of 10 CFR 50.92.

Page 3/4 3-31, the correct values are contained in the final Westinghouse Setpoint Study. The values currently contained in Technical Specification Table 3.3-4, Item 8.c are from a prior Setpoint Study. Technical Specification Table 2.2-1, Item 13 contains the same trip function, however the numbers reflected there are correct. Thus, due to an oversight, the values in Table 3.3-4 did not get revised appropriately and should be corrected.

Page 3/4 3-52, there are two separate intakes for the control room each with one radiation monitor channel for a total of two channels for the station.

Page 3/4 8-7, an administrative error needs to be corrected in that the electrolyte level needs to remain below, not above, the high mark.