Text

Forwards Proposed Amends to Draft Tech Specs Re Area Temp Monitoring,Containment Bldg Penetrations,Overpressure Protection Sys,Containment Pressure Control Sys & Turbine Overspeed Protection
	ML20091N440
Person / Time
Site:	Catawba
Issue date:	06/05/1984
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 8406120316
	Download: ML20091N440 (22)
	v • d • e

DUKE POWER GOMPANY P.O. BOX 33180 i

CD AHLOTTE, N.C. 28242 l

HAL B. TUCKER vetepiroxz vnosparatoes?

(704) GN531 Jure 5,-1984 s

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 Draft Technical Specifications

Dear Mr. Denton:

Attachments 1-5 of this letter contain proposed amendments to the Draft Technical Specifications for Catawba Unit 1.

Each attachment contains the proposed changes and a discussion of the justification.

Very truly yours, MM Hal B. Tucker RWO/php Attachments

-cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Comission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.

Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 E

Mr. Jesse L. Riley.

- Carolina Environmental Study Group

-854~Henley Place Charlotte, North Carolina 28207 8406120316 840605

-Palmetto Alliance PDR ADOCK 05000413 1

A PDR

\\

21351 Devine. Street Columbia,-South Carolina 29205-1'

e J

Proposed Amentc.ent to Catawba Unit 1 Draft Technical Specification 3.7.12 Concerning Area Temperature Monitoring 6

r s

W.

C 15

\\

>2 p

_'y+e is.---

o y

c

., Page 1 The proposed change would delete Technical Specification 3/4.7.12, Area Temperature Monitoring.

In accordance with 10 CFR 50.49 and in response to NUREG-0588 and SER Open Item 4, Duke submitted information pertaining to the environmental qualification of electrical and mechanical equipment important to safety.

These submittals are dated June 17, 1982, February 7,1984, February 8,1984, March 16, 1984, April 16, 1984 and April 25, 1984. Meetings were held on February 8,1984 and March 6, 7, and 8,1984 between members of the NRC Staff and Duke Power employees to discuss these submittals and to conduct an environmental qualification audit at Catawba.

For equipment required to perform a safety function in a harsh environment, environmental qualification including the effects of aging are addressed in the qualification program as required by 10 CFR 50.49 and NUREG-0588. For electrical equipment located in a mild environment, the NRC has stated in the Statement of Consideration for 10 CFR 50.49 (Comments on the Proposed Rule, Paragraph (3), Scope) that "the Commission has concluded that the general quality and surveillance requirements applicable to electric equipment as a result of the Commission regulations, including 10CFR. 50; Appendix B, are sufficient to ensure adequate performance of' electric equipment important to safety located in mild environments."

Based on the Catawba equipment qualification program and preventive maintenance and surveillance programs, it is concluded that an area temperature monitoring system as described in Technical Specification 3/4.7.12 is not required at Catawba.

l Page 2 Y

'A LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6.5 ICE CONDENSER Ice Bed..................................................

3/4 6-33 Ice Bed Temperature Monitoring System....................

3/4 6-35 Ice Condenser Doors......................................

3/4 6-36 Inlet Door Position Monitoring System....................

3/4 6-38 Divider Barrier Personnel Access Doors and Equipment Hatches......................................

3/4 6-39 Containment Air Return and Hydrogen Skimmer Systems......

3/4 6-40 Floof Drains.............................................

3/4 6-42 Refueling Canal Drains...................................

3/4 6-43 Divider Barrier Seal.....................................

3/4 6-44 TABLE 3.6-3 DIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES...

3/4 6-45 3/4.6.6 CONTAINMENT VALVE INJECTION WATER SYSTEM................

3/4 6-46 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves............................................

3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION......................................

3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY. VALVES PER L00P.....................

3/4 7-3 Auxi l i ary Feedwate r System...............................

3/4 7-4 Specific Activity........................................

3/4 7-6 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................

3/4 7-7 Main Steam Line Isolation Valves.........................

3/4 7-8 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-9 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-10 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................

3/4 7-11 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND.......................

3/4 7-12 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM.....................

3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM...

3/4 7-16 3/4.7.8 SNUBBERS.................................................

3/4 7-18 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST...........

3/4 7-23 3/4.7.9 SEALED SOURCE CONTAMINATION..............................

3/4 7-24 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................

3/4 7-26 Spray and/or Sprinkler Systems...........................

3/4 7-28 CO, Systems..............................................

3/4 7-30 FiPe Hose Stations.......................................

3/4 7-32 TABLE 3.7-3 FIRE HOSE STATIONS....................................

3/4 7-33 3/4.7.11 FIRE BARRIER PENETRATIONS................................

3/4 7-35

-3/4.7.12 ^9E? TEMIERATURE MONITORI E

.=

m

--._ -3/4 7 M

"^2LE 3. 7-4 AREA TEMTERATURE NQM-TORfNG..%-

3/4.7. p GROUNDWATERLEVEL........................................

- 3/" 7 X 3/4 7-36' IL S

l CATAWBA - UNIT 1 VII l

Page 3 BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.............

B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK................../...........

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................

B 3/4 6-4 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 3/4.6.5 ICE CONDENSER.............................................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.............................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

B 3/4 7-2 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER-SYSTEM..............................

B 3/4 7-3 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND........................

B 3/4 7-3 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM......................

B 3/4 7-3 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM....

B 3/4 7-4 3/4.7.8 SNUBBERS..................................................

B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS..................................

B 3/4 7-6 3/4.7.11 FIRE BARRIER PENETRATIONS.................................

B 3/4 7-7 3/4.7.1^ AREA TErrtxaiunE riGMTGRis 0 3/4 7 7-3/4.7.{12 GROUNDWATER LEVEL.........................................

B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, ONSITE POWER DISTRIBUTION..............................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...................

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-1 3/4.9.3 DECAY TIME................................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................

B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE.........................................

B 3/4 9-2 CATAWBA - UNIT 1 XI

Page 4 XLANT SYSTEMS

(

^

3/

12~ AREA TEMPERATURE MONITORING ik LIMITING C DITION FOR OPERATION x

3.7.12 The temp ature of each area shown in Table 3.7-5 shal not be exceeded for more an 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or by more than 30*F.

APPLICABILITY:

_ Whenever the equipment in an affected are is required to be OPERABLE.

ACTION:

a.

With one or more areas e eeding the te erature limit (s) shown in Table 3.7-5 for more th 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , repare and submit to the Commission within 30 ys, pu uant to Specification 6.9.2, a Special Report that provides r ord of the cumulative time and the amount by which the temperat e in the affected area (s) exceeded the limit (s) and an analysis to e onstrate the continued OPERABILITY of the affected equipment.

'b.

With ~one or more areas ex eding the te erature limit (s) shown in Table 3.7-5 by more,tha 0 F, prepare an submit a Special Report as required by ACTION a.

ove and within 4 he s either restore the area (s) to within t temperature limit (s) or eclare the equipment in the affected ar a(s) inoperable.

SURVEILLANCE REQUIREM TS x

4.7.12 The t perature in each of the areas shown in Table 3.7-5 shall e

determined be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i l

l l

CATAWBA - UNIT 1 3/s 7 37 -

e9 #

Page 5 r-- ~

TABLE 3.7-4 g[

p g

AREA TEMPERATURE MONITOR AREA 1PERATURE LIMIT ( F) 1.

2.

3.

4. -

5.

,6 D

THIS PAGE OPEN PENDING RECEIPT OF INFORMATION ROM THE APPLICANT W

a W

CATAWBA - UNIT 1 2/' 7 7 Page 6 PLANT SYSTEMS i)RA r a

3/4.7.M GROUNDWATER LEVEL LIMITING CONDITION FOR OPERATION I2-3.7.M The groundwater level shall be maintained at or below the top of the adjacent floor slabs of the Reactor Containment Building and the Auxiliary Building.

APPLICABILITY: At all times.

ACTION:

a.

With the groundwater level above the top of the adjacent floor slab by less than or equal to 5 feet, reduce the groundwater level to or below the top of the affected adjacent floor slab within 7 days 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 the groundwater level above the top of the adjacent floor slab by greater than 5 feet but less than 15 feet, reduce the groundwater level to less than or equal to 5 feet above the top of the affected adjacent floor slab within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and to or below the top of the affected adjacent floor slab within 7 days of initially exceeding the above limits 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 .

With the groundwater level above the top of the adjacent floor. slab c.

by greater than or equal to 15 feet, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Perform an engineering evaluation of determine the effects of this higher groundwater level on the affected building (s) and submit the results of this evaluation and any corrective action determined necessary to the Commission as a Special Report pursuant to Specifi-cation 6.9.2 prior to increasing T,yg above 200 F.

d.

Determine the rate of. rise of groundwater when the level reaches the top of the floor slab.

If the rate of rise of the groundwater level is greater than or equal to 0.3 feet per hour, determine the rate of rise at least once per 30 minutes.

If the rate of rise exceeds 0.5 feet per hour for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If the rate of rise is less than 0.5 feet per hour, comply with the requirements of ACTIONS a. b. and c. above.

8 CATAWBA - UNIT 1.

3/47-J(

f w

s Page 7 p )j PLANT SYSTEMS L i \\r![ i SURVEILLANCEREQUIRkMENTS l

1%

4.7.34" The groundwater level shall be determined at the following frequencies by monitoring the water level and by verifying the absence of alarm in the six groundwater monitor wells as shown in FSAR Figure 2.4.13-14 installed around

~

the perimeter _of the Unit 1 Reactor and Auxiliary Building:

a.

At least once per 7 days when the groundwater level is at or below the top of the adjacent floor slab, and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the groundwater level is above the top of the adjacent floor slab.

t 4

f a

f l

l g6 CATAWBA - UNIT 1 3/47,4(

4 4

Page 8 PLANT SYSTEMS I'

8ASES FIRE SUPPRESSION SYST WS (Continued)

In the event the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

3/4.7.11 FIRE BARRIER PENETRATIONS The functional integrity of the fire barrier penetrations ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

These design features minimize.the possibility of a single fire rapidly involving several areas of the facility prior to detection and extin-guishing of the fire. The fire barrier penetrations are a passive element in the facility fire protection program and are subject to periodic inspections.

Fire barrier penetrations, including cable penetration barriers, fire doors, fire dampers, and other fire barriers are considered functional when the visually observed condition is the same as the as-designed condition.

For those fire barrier penetrations that are not in the as-designed condition, an evalua-tion shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.

During periods of time when a barrier is not functional, either:

(1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or (2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established, until the barrier is restored to functional status.

2/t.'.12 ARCA TCICRATURE nGNITGRI:;0 The Orc: t;..,; r:tu r: '*-1t:tica; ;.:ure th:t ::fety-rel t:d ;;ui;;c.t

" r.at to owvg Ged i: t ;;r:tur:: i cree : ef th:i cr"ir:r :nt ! ';2:!'-

44 :t!:n t::;:r:tur::.

Expe:ur; te m e;;f;: t^ pa stur":

y de r d" aa"4a=an*

"d

r :n;e ; 1;;; ef it; OPERACILIT'/.

Tl.m

..scr

ture li-it: 'nc!rd n

lln::n:: #a- # 9:t r ent crre, of i 3.3'h 12.

3/4.7.M GROUNDWATER LEVEL This specification is provided to ensure than groundwater levels will be monitored and prevented from rising to unacceptable levels.

High ground-water levels could result in unacceptable structural stresses in the Contain-ment and/or Auxiliary Building due to uplift and hydrostatic forces during design basis events. Although these buildings have been statically analyzed to withstand soil pressure along with the uplift and hydrostatic forces resulting from groundwater rebound to yard elevation (593'6"), this analysis did not include any other loadings and was not a design condition for these buildings.

CATAWBA - UNIT 1 B 3/4 7-7

-,,-4

" * ' ~ * ' " '

g l},

4 Proposed Amendment to Catawba Unit 1 Draft ~

s.

! Technical Specification 4.9.4.2.a Concerning

-Containment Building Penetrations 7

1, Page 1

'l The proposed change would delete the requirement to initiate Containment Purge flow "from the control room."

f This change is required because the nonnal operation of this system is done from a control panel which is not located inside of th2 control room.

4 d'

i t.

' i I.,

. _ _. Page 2 i

REFUELING OPERATIONS l

SURVEILLANCE REQUIREMENTS (Continued) 3 4.9.4.2 The Reactor Building Containment Purge System shall be demonstrated OPERABLE:

i

~

J At least once per 31 days by initiatingr -w - m.t.-

- _ flow a.

F through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; 1

b.

At 1. east 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 communi-cating with the system by:

1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedures guidance in Regula-tory Positions C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 28,000 cfm 10% (both exhaust fans operating);

2)

Verifying within 31 days after removal, that a laboratory analysis of a presentative carbon sample obtained in accordance with Regulatory. Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.5,2 Revision 2, March 1978, for a methyl iodide penetration of less than 6%;

and 3)

Verifying a system flow rate of 28,000 cfm i 10% (both exhaust fans operating) during system operation when tested in accordance with ANSI N510-1980.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying, c.

within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, 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 6%;

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters, charcoal adsorber banks, and moisture separators is less than 8 inches Water Gauge while operating the system at a j

i flow rate of 28,000 cfm i 10% (both exhaust fans operating);

2)

Verifying that the filter cooling bypass valves can be opened t

by operator action; and CATAWBA - UNIT 1 3/4 9-5

.y..

.~

-1

,7_f-

b y

t i

f J

4 4

4 -

j.

e l

Proposed Amendmerit to Catawba Unit 1 Draft Technical Specification 3.4.9.3 Concerning Overpressure Protection Systems t'

4 J

D i

~

t p

k b'

c" t'

i 1

--j

?

~

.'?'*

[L p':

4 h,Y

^

4,

F Page 1 4

}

'The proposed' revision would change the lift setting for the power operated r'elief valves from "less than or equal to 400 psig" to "less than or equal to 450 psig." The change is required to provide an allowance for possible drift and instrument error.

FSAR' Table 5.4.13-1 and station procedures specify a lift setting of 400 psig.

- Increasing the lift setting in the Technical Specifications will allow operating 4

flexibility and avoid a Technical Specification violation if instrumentation drifts.

The lift setting will remain at 400 psig per the station procedures. The Surveillance Requirements to verify this setpoint will also remain the same.

An inspection of the Heatup and Cooldown curves shows that there is a negligible difference between the limitations at 400 psig and 450 psig. Thus, if the

,setpoints drift up to 450 psig, the margin of safety would be insignificantly

- reduced.

i L

4 f

l

.yl '

s A

g; g _

g e

s,.,.

u 4

e

-s.e,-..n.,,,,.-,.mm..m,-

m, g

Page 2 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:

Two p'than or equalower operated relief valves (PORVs) with a lift setting a.

less or b.

The Reactor Coolant System depressurized with a Reactor Coolant System vent of greater than or equal to 4.5 square inches.

APPLICABILITY: MODE 4 when the temperature of any Reactor Coolant System cold leg is less than or equal to 285*F, MODE 5 and MCDE 6 with the reactor vessel head on.

ACTION:

With one PORV inoperable, restore the inoperable PORV to OPERABLE a.

status within 7 days or depressurize and vent the Reactor Coolant System through at least a 4.5 square inch vent within the next

-8 hours.

b.

With both PORVs inoperable, depressurize and vent the Reactor Coolant System through at least a 4.5 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

In the event either the PORVs or the Reactor Coolant System vent (s) c.

are used to mitigate a Reactor Coolant System 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 Reactor Coolant System vent (s) on the transient, and any corrective action necessary to prevent recurrence.

d.

The provisions of Specification 3.0.4 are not applicable.

9 9

CATAWBA - UNIT 1 3/4 4-36

Proposed Amendment to Catawba Unit 1 Draft Technical Specification Table 3.3-4 Item 7. Containment Pressure Control System

. Page 1 The proposed change would revise the Setpoints and Allowable Values for the Containment Pressure Control System.

The current Setpoints and Allowable Values are all the same. The as-built system cannot start'and terminate at the same setpoint.

In addition, there is no allowance for instrument error or drift.

.The proposed Setpoints and Allowable Values are consistent with the FSAR analyses and will allow needed flexibility in the operation of the system.

1 2=

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS s

SENSOR i

TOTAL ERROR g

FUNCTIONAL UNIT ALLOWANCE (TA)

Z, (S)

TRIP SETPOINT ALLOWABLE VALUE

[

6. Turbine Trip a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation N.A.

N.A.

Logic ~and Actuation: Relays

,/

c.

Steam Generator Water 5.4 2.18 1.5

< 82.4% of

< 84.2% of narrow Level-High-High (P-14) iiarrow range range instrument instrument span

,'g span d.

Trip of All Main N.A.

N.A.

,Y Feedwater Pumps O

y e.

Doghouse Water Level-High 1.0 0

0.5 11 inches 12 inches above 1.9 above 577' 577' floor level floor level f.

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

A 75 Containment Pressure Control w

System 9

2

.f 4 o. 84 5 a.

Start Permissive N.A.

N.A.

_N.A.

j id prri a

b.

Termination N.A.

N.A.

L 25 psid p 'd 2

8. Auxiliary Feedwater t 'so E

~

m a.

Man ~ual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays

3 A

Proposed Amendment to Catawba Unit 1 Draft Technical Specification 3/4.3.4 Concerning Turbine Overspeed Protection

.c f

r-r d

F

?

. ~:

_w: -

. Page 1 Catawba Technical Specification 3.3.4 states that at least one Turbine Overspeed Protection System shall be operable in Modes 1, 2, and 3 if any one Main Steam Isolation or Main Steam Isolation By-Pass valve is not fully closed. To prove operability, per Catawba Tech Spec Item 4.3.4.2.a. all turbine valves must complete a full cycle of travel from the running position.

This is, with slight modification, a direct quote from NUREG-0452 Rev. 4

" Standard Technical Specifications for Westinghouse Pressurized Water Reactors" which are applicable to plants utilizing Westinghouse NSSS and B0P systems, including Westinghouse turbines and control systems. The Westinghouse turbine control system design will allow testing of this nature prior to turbine start-up utilizing normal operating procedures. Catawba utilizes a General Electric turbine and control system which does not lend itself to this type of test using normal operating procedures.

In order to test all the turbine valves prior to turbine start-up, the Electro-hydraulic Control System would require a temporary modification of the electronic circuits to allow the turbine valve groups (i.e., Stop, Control, Intercept, and Reheat Stop valves) to reposition to the " running position." Manipulation of the electronic circuits would cause the bypassing of circuits incorporated to protect the turbine from themal transients and overspeed during normal turbine start-up and enhance turbine degradation. An alternative would be cycling the turbine valves as they are operated during a nomal start-up.

By performing the test during the normal start-up period, there would be no abnormal valve alignment other than a valve being misaligned to the " closed" position, which is more conducive to safe operations. During a normal start-up, the Turbine Control Valves and Reheater Stop Valves are cycled prior to opening the Main Stop Valves and rolling the turbine (these valves are the secondary line of defense against turbine over-speed). After waming the turbine steam chest and shell, the turbine is brought to synchronous speed (1800 rpm). Once 1800 rpm is reached and control is stabilized, the Main Stop Valves (primary overspeed protection) and the combined Isolation Valves may be cycled.

Therefore, in order to be able to prove turbine valve operability during start-up of the turbine, the Catawba Tech Spec must be changed as indicated.

I I

e..-

- Page 2 INSTRUMENTATION

)

J j

3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION

^

3.3.4 At least one TurbineAvtfrs otection System shall be OPERABLE.

/

APPICABILITY: MODE 1,2 C W ACTION:

and With one stop valve or one control valve per high pressure turbine a.

steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the above required Turbine Overspeeo Protection System otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

At least once per 7 days by cycling each of the following valves a.

through at least one complete cycle from the running position:

1)

Four high pressure turbine stop valves, 2)

Four high pressure turbine control valves, 3)

Six low pressure turbine intermediate stop valves, and 4)

Six low pressure turbine intercept valves.

b.

At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position.

l c.

At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection, Systems, and d.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosionm

\\

? _: 5 r 6 :1:

. _e_m :m = === =~ = = " = ' = * =

CATAWBA - UNIT 1

/4-3 #

u W este e

ML20091N440

Text

Dear Mr. Denton:

Navigation menu

Search