ML20101J076

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Proposed Tech Specs,Proposing to Revise TS to Implement 24 Month Plant Refueling Cycle Which Includes Operating Cycle & One Refueling/Maintenance Outage
ML20101J076
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/24/1992
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20101J062 List:
References
NUDOCS 9206300331
Download: ML20101J076 (18)
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Text

.

ATTACHMENT Technical Specification Change P

e 9

1.2.7 REFUELING OPERATION An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.2.8 REFUELING INTERVAL Time between normal refuelings of the' reactor.

This is defined as once per 24 months.

1.2.9 STARTUP The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

1.2.10 T,,

T,,, is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating, if such a distinction of loops can be made.

1.2.11 HEATUP - C00LDOWN MODE The heatup-cooldown mode is the range of reactor coolant temperature greater than 200*F and less than 525aF.

1.2.12 STATION, UNIT, PLANT, AND FACILITY Station, unit, plant, and facility as used in these technical specifications all refer to TMI Unit 1.

1.3 OPERABLE l

A system, subsystem, train, component or device shall be OPERABLE or have i

OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, i

cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

1.4 PROTECTION INSTRUMENTATION LOGIC 1.4.1 INSTRUMENT CHANNEL An instrument--channel is the combination of sensor, wires, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control, and/or protection.

An instrument channel may be either analog or digital.

i I

l 1-2 Amendment No. 9S, 157

m w.__

1.19 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement, j

1.20 VENTING VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in_such a manner that replacement air or gas is not provided.

Vent used in system name does not imply a VENTING process, i

1.21 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

1.22 MEMBER (S) 0F THE PUBLIC i

MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the i

GPU System, GPU contractors or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

l.23 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent.

Examples _of non-subscantive i

changes are: (1) correcting spelling; (2) adding (but not deleting) sign-off spaces; (3) blocking in notes, cautions, etc.; (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Appendix A Technical Specifications; and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

1.24 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is a TMl-1 specific document that nrovides core operating limits for tho current operating reload cycle.

Toese cycle-specific core operating limits shall be determined for each reload cycle in accordau:e with Specification 6.9.5.

Plant operation within these operating liinits is addressed in individual specifications.

4 I'.25 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the -intervals defined in Table 1.2.

All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of_"F."

No extension is allowed for intervals designated "F."

l-7 Amendment No. 77, D 7, HJ, J R, JM, J57, 158

TABLE 1.2 i

FRE0VENCY NOTATION i

NOTATION FRE0VENCY S

Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

D Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

W Weekly (once per 7 days)

M Monthly (once per 31 days)

Q Quarterly (once per 92 days)

S/A Semi-Annually (once per 184 days)

R Refueling Interval (once per 24 months)

P S/U Prior to each reactor startup, if not done during the previous 7 days P

Completed prior to each release N/A (NA)

Not applicable E

Once per 18 months F

Not to exceed 24 months BUli Section 1.25 establishes the limit for which-the specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that uay not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with a fuel cycle length surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance interals beyond that specified for surveillances that-are not performed during refueling outages.

The limitation of Section 1.25 is based on engineering judgement and the recognition that the most probable result of-any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that-the reliability ensured through surveillance activities is not significantly degraded-beyond that obtained from the specified surveillance interval.

1-8 Amendment No. 72, U/, 155 L

3 e

L

- F TACLE 4.1-1

8

['

INSTRUMENT SURVEILLANCE REQUIREMENTS

(

J E

CHANNEL DESCRIPTION CHECK TEST CALIBRATE REF. ARKS-

~

E

'l.

' Protection Channel NA-M NA

. Coincidence' Logic

2.. Control Rod Drive Trip NA M

.NA (1)

Includes independent' testing of shunt.

t Breaker-and Regulating trip and'undervoltage. trip features.

Rod Power SCRs-i w

3. - Power Range. Amplifier -

D(1)

NA (2)

(1) When reactor power is greater than 15%.

(2). When above 15% reactor. power run'a heat' l

balance check once per shift. Heat balance calibration shall be performed' i

whenever heat balance exceeds indicated neutron power by more than two percent.

i

[

4.

Power Range Channel S.

M M(1)(2) (1) When reactor power is greater than 60%

. verify imbalance using incore r

instrumentation.

{

(2) When above:15% reactor power calculate axial offset upper and lower chambers after each startup if not done within 3

J the previous seven days.-

{

5.

Intermediate" Range Channel S(1)

PS/U.

NA.

-(l) When in. service.

i

6.. Source Range. Channel S(l)

PS/U NA-(1) When in' service.

4 l

i 7.

Reactor Coolant-Temperature S.

M F

Channel h

4 t

4 I

i 5

i w

,U.

N

'761

'r*

-6

~

--m---------a g

!i TABLE 4.1-1 (Continued)

CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS A

8.

High Reactor Coolant S

M R

2 Pressure Channel o

w*

19. Low Reactor Coolant S

M R

Pressure Channel

,o

10. Flux-Reactor Coolant Flow S

M F

02 Comparator

?

11. (Deleted)
12. Pump Flux Comparator S

M R

13. High Reactor Building S

M F

Pressure Channel

14. High Reactor Building NA Q

NA P

Logic Channels a

15.'High Pressure Injection Analog Channels a.

Reactor Coolant S(1)

M R

(1) When reactor coolant system is Pressure Channel pressurized above 300 psig or T,,,is greater than 200=F.

16. Low Pressure Injection NA Q

NA Logic Channel

17. Lower Pressure Injection Analog Channels a.

Reactor Coolant S(1)

M R

(1) When reactor coolant system is Pressure Channel pressurized above 300 psig or T,,,is greater than 200*F.

18. Reactor Building Emergency NA Q

NA Cooling and Isolation' System Logic' Channel

if 4

I TABLE 4.1-1 (Continued) if CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS

[

g R.

19. Reactor Building Emergency s

Cooling and Isolation-

[

-System Analog Channels i

O i

a. Reactor Building S(l)

M(1)

F (1) When CONTAINMENT INTEGRITY is required.

2 4 psig Channels

b. RCS~ Pressure 1600.psig S(1)

M(1)

NA (1) When RCS Pressure > 1800 psig.

E d.'RPS Trip S(l)

M(1)

NA (1) When CONTAINMENT INTEGRITY is required.

i c.

Reactor Bldg.'30lpsig S(l)

M(1)

F (1) When CONTAINMENT INTEGRITY is required.

l O

e. Reactor Bldg.: Purge W(1)

M(1)

F (1) When CONTAINMENT INTEGRITY is required. ;

Line'High~ Radiation (AH-V-1A/0)

~

1

f. Line Break Isolation W(1)

M(1)

R (1) When CONTAINMENT INTEGRITY is required.

' Signal (ICCW & NSCCW) l m

t

20. Reactor building. Spray NA

.Q NA System. Logic-Channel

21. Reactor Building; Spray i

System Analog Channels.

y i

f a.: Reactor Building-NA:

M F

~

30 psig Channels.

1

22. Pressurizer Temperature S

NA R

i Char.nels i

23.' Control Rod Absolute' Position S(1)

NA R

(1) Check with Relative Position Indicator.

.24. Control ' Rod Relative Position.

S(1)

NA-R (1) Check with' Absolute Position Indicator.

25. Core ~ Flooding. Tanks
a. Pressure Channels-

'S(l)

NA' F

(1) When Reactor. Coolant' system pressure is

' greater.than 700 psig.

b. Level. Channels' S(l)~

NA F

[

26. Pressurizer' Level Channels S'

.NA-R l

ij.

.~

F TABLE 4.1-1 (Continued) 8-CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS 3

27. Makeup Tank Level Channels D(1)

NA F

(1)' When Makeup and Purification System is l 8F in operation.

js

28. Radiation Monitoring Systems
  • W(I)(3) M(3)

Q(2)

(1) Using the installed check source when background is less than twice the

j expected increase in cpm which would result from the check source alone.

Background readings greater than this y*

value are sufficient in themselves to show that the monitor is-functioning.

E (2) Except area gamma radiation monitors 0

RM-G5, RM-G6, RM-G7 and RM-G21 which are located in the Reactor Building. When purging is permitted per T.S. 3.6, RM-GS

~

ll and RM-G21 will be calibrated quarterly.

If purging is not permitted per T.S.

Og 5, 3.6, RM-G5 and RM-G21.shall be calibrated at the next scheduled reactor shutdown following the quarter in which calibration would normally be due.

RM-G6 and RM-G7, which are in high radiation areas shall be calibrated at the next scheduled reactor shutdown following the quarter in which calibration is due, if a shutdown during the quarter does not occur.

(3) Surveillances are required to be performed only when containment integrity is required. This applies to monitors which initiate containment isolatios only.

29. High and Low pressure-N/A N/A F

Injection Systems:

Flow Channels

  • Does not include the monitors covered under Specification 3.5.5.2 and 4.1.3 or Specification 3.21.1, 3.21.2 and 4.21.1, 4.21.2.

TABLE 4.1-1 (Continued)

CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS

30. Borated Water Storage W

NA F

' Tank Level 1 Indicator

-31.. Boric Acid Mix-Tank a.: Level Channd

'NA NA F

b. Temperature Channel M

NA F

32. Reclaimed Borici Acid Storage Tank-

~

a. Level Channel NA NA F-
b. Temperature Channel _

M NA F

y

33. Containment'. Temperature NA.

NA F

34. Incore Neutron Detectors M(1)

NA NA (1) Check functioning'; including functioning of computer readout or recorder' readout when reactor power is grater than 15%.

35.' Emergency Plant Radiation M(1)

NA F

(1) Battery check.

1

. Instruments 3

36. Strong Motion Acce'lerometer Q(1).

NA Q-(1) Battery check.

37. Reactor Building Sump.

NA NA R

Level-

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

3 TABLE 4.1-1 (Continued)-

8.

t i

CHANNEL DESCRIPTION

- CHECK TEST CALIBRATE REMARKS 8

38. OTSG Full Range level-W NA R

5' 39.ITurbine OverspeecFTrip NA R

NA' e

i

40. BWST/NaOH Differential NA NA F

y Pressure Indicator

41. Sodium Hydroxide' Tank-NA NA F

Level. Indicator M

?

42. Diesel Generator Protective' NA NA

- R Relaying 5

.43. 4 KV ES' Bus Undervoltage

~

Relays (Diesel Start)

a. Degraded Grid-NA M(1)

R

' (1) Relay operation will be checked by local.

u.

test pushbuttons.

b. Loss of Voltage NA M(1)

R (1) Relay operation will be checked by local test pushbuttons.

44.: Reactor Coolant: Pressure-.

S(l)

M R

(1) When reactor coolant system is DH Valve: Interlock Bistable pressurized above-300 psig or Tm.is -

greater than 200*F.

i

45. Loss'of:Feedwater: Reactor Trip-

-S(1)

M(1)-

- R (1) 'When' reactor power exceeds 7% power.

46. Turbine. Trip / Reactor Trip S(1)

M(1).

F (1)- When reactor power exceeds 45% power.

y

47. :a.: Pressurizer Code: Safety Valvel

-S(1)

'NA F

l(1) When T is greater than 525*F.

'm

.-and PORY Tailpipe Flow Monitors t

b.HPORV_.

Acoustic / Flow.

NA-M(1).

R-'

' s greater than 525'F.

(1) When T i

m E48.'PORV.Setpoints NA-M(1)

R-

.(1)

Per Specification 3.1.12 excluding valve operation.

t i

.. m.

2 a.

=.

s

ra p

TABLE 4.1-1 (Continued) g CHANNEL DESCRIPTIOP CHECK TEST CALIBRATE REMARKS S

5

49. Saturation Margin Monitor S(l)

M(1)

R (1) When T is greater than 525'F.

m

50. Emergency Feedwater Flow NA M(1)

F (1) When T is greater than 250*F.

m g

Instrumentation O

51. Heat Sink Protection System
a. EFW Auto Initiation (1)

Includes logic test only.

2 Instrument Channels

1. Loss of Both Feedwater Pumps NA Q(1)

F

{

O

2. Loss of All RC Pumps NA Q(1)

R

3. Reactor Building Pressure NA Q

F l

4. OTSG Low Level W

Q R

-?

b. MFW Isolation OTSG Low Pressure NA Q

R

% e7

c. EFW Control Valve Control System
1. OTSG Level Loops W

Q R

2. Controllers W

NA R

d. HSPS Train Actuatior Logic NA Q(1)

R

52. Backup Incore Thermocouple Display M(1)

NA R

(1) When T is greater than 250*F.

m

53. Cnlorine Detection System W

M F(l)

(1) Calibrationisaoneconcentrationpointl Instrumentation check (need not be traceable to NBS standards).

54. RCS Inventory Trending System
a. Level NA NA F
b. Void Fraction W

NA F

L

TABLE 4.1-2 HINIMUM EQUIPMENT TEST FREQUENCY jim lui freauency 1.

Control Rods Rod drop times of all Each Refueling shutdown full length rods 2.

Control P.od tiovement of each rod Every two weeks, when Movement reactor is critical 3.

Pressurizer setpoint*

50% each refueling period Safe') Valves 4.

Main St' m Setpoint Approximately 50% each Safety Valves refueling period L

Refueling System Functional Start of each Interlock.s refueling period 6.

Main Steam (See Section 4.8)

Isolation Valves 7.

Reactor Coolant Evaluate Daily, whtn reactor System Leakage coolant system temperature is greater then 525'F 8.

(Deleted) 9.

Spent Fuel Functional Each refueling period Cooling System prior to fuel handling

10. Intake Pump (a) Silt Accumulation-Not to exceed 24 months House Floor Visual inspection (Elevation of Int.ne Pump 26~ ft. 6 in.)

House Floor

.(b) Silt Accumulation Quarterly Measurement of Pump House Flow

11. Pressurizer Block Functional **

Quarterly Valve (RC-V2) l

  • The setpoint of the pressurizer co'de safety valves shall be in accordance with ASME Boiler and Pressurizer Vessel Code,Section III, Article 9, Winter, 1968.
    • Function shall be demonstrated by operating the valve through one complete cycle of full travel.

4-8 Amendment No. 5), $5, 7S, 149 i

[

TABLE 4.1-4

[

POST ACCIDENT MONITORING INSTRUMENTATION A

FUNCTION INSTRUMENTS CHECK TEST CALIBRATE REMARKS 5

1.

Noble Gas Effluent g

a.

Condenst Vacuum Pump Exhaust W

M F

(1) Using the installed check-(RM-AS-Hi) source when background is less a

than twice the expected increase in cpm which would result from the check source alone.

Background readings greater than this value are sufficient in themselves to show that this monitor is functioning.

b.

Condenser Vacuum Pump Exhaust W(1)

M F

(RM-G25) c.

Auxiliary and Fuel Handling W

H F

Building Exhaust (RM-AS-Hi) d.

Reactor Building Purge Exhaust W

M F

(RM-A9-Hi) e.

Reactor Building Purge Exha>st W(1)

M F

(K;i-G24) f.

Main Steam Lines Radiation W(1)

M f

(RM-G26/RM-G27) 2.

Containment High Range Radiation W

M R

(RM-G22/G23) 3.

Containment Pressure W

N/A F

4.

Containment Water Level W

N/A R

5.

Containrent Hydrogen W

M F

6.

Wide Range Neutron Flux W

N/A F

e__.

=

[

TABLE 4.1-4 (Continued)

POST ACCIDENT MONITORING INSTRUMENTATION

',Ei FUNCTION INSTRUMENTS CHECK TEST CALIBRATE REMARKS 7.

Reactor Coolant Systete Coli Leg W

N/A R

t

-Water Temperature (TE-957, 961; TI-9E)A, 961A)

8..

Peactor Coolant System Hog Leg W

N/A R

j (TE-958, 960; TI-958A, 960A) t t

9.

Reactor Coolant System Pressure W

N/A R

(PT-949,963: PI-949A,963) 10.

. Steam Generator Pressure W

N/A R

(PT-950, 951,.1180, 1184;

.PI-950A,951A,1180,1184) i

[

11.

Condensate Storage Tank Water Level W

N/A F

g (LT-10CO, 1061; 1062, 1063; i

LI-1050,1061,1062,1063) 4 i

[

I 4.4.4 Ryfirocen Recambiner System Anolicability Applies to the testing of the hydrogen recombiner and associated controls.

Ob.iective To verify that the hydrogen recombiner and associated controls are operable.

4.4,4.1 Speci fication a.

At least once per 6 months, perform a hydrogen recombiner system functional test to demonstrate that the minimum reaction chamber gas temperature is maintained 1600*F for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b.

At least once per refueling interval, perform the following surveillances:

1.

A channel calibration of all recombiner instrumentation and control circuits (interval not to exceed 24 months),

i 2.

Verify through a visual examination that there is no evidence of abnormal conditions (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3.

Verify during a recombiner system functional test that the reaction chamber gas temperature is maintained 21200*F for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.

Verify the integrity of the heater electrical circuits by performing a continuity and resistance to ground test. The resistance to ground for any heater phase shall be 210,000 ohms.

Eliti The surveillance program described above provides high assurance that the hydrogen recombiner system will be available to perform its post-LOCA function of maintaining the containment hydrogen concentration below 4.1 volume percent.

This system is not credited to mitigate any accident analyzed in Chapter 14 of the TMl-1 FSAR.

The frequency of the survelliance of the hydrogen recombiner system is based on the safety significance of the system.

THI-l FSAR Section 6.5.3.1 indicates that the hydrogen recombiner system is not required until 9.8 days following a LOCA.

This is adequate time to place a hydrogen recombiner in service.

4 4 38 Amendment No. S7,.158

4.12 AIR TREATMENT SYSTEM 4.12.1 EMERGENCY CONTROL ROOM AIR TREATHENT SYSTEM Aeolicabilitv Applies to the emergency control room air treatment system and associated components.

Ob.iect in

(

To verify that this system and associated components will be able to perform its design functions.

EpnificatiqD 4.12.1.1 At least every refueling interval, the pressure dro) across the combined HEPA filters and charcoal adsorber ban (s of AH-F3A and 3B shall be _ demonstrated to be leas than 6 inches of water at system design flow rate (110%).

4.12.1.2 a.

The tests and sample analysis required by Specificatici.

3.15.1.2 shall be aerformea initially and at least once per year for standay service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, steam, fire or chemical release in any ventilation zone cor.municating with the system that could contaminate the HEPA filters or charcoal adsorbers, b.

00P testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing ethich could affect the HEPA filter bank bypass leakage.

c.

Halogenated hydrocarbon testing shall be )erformed after each complete or partial replacement of 11e charcoal adsorber bank or after any structural maintenance cn the system housing which could effect the charcoal-adsorber bank bypass leakage, d.

Each AH-E18A and B (AH-F3A and B) fan / filter circuit shall be operating at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.

4.12.1.3 At least once per refueling interval, automatic initiation of the Control Building isolation and recirculation Dampers AH-D28, 37, 39, and 36 shall be demonstrated as operable.

4.12.1.4 An air distribution test shall be performed on the HEPA filter bank initially, and after any maintenance or testing that could affect the air distribution within the system.

The air distribution across the HEPA filter bank shall be uniform.

within 20%. The test shall be performed at 40,000 cfm (i10%)

flow rate.

4-55 Amendment No. 55, SS, 149

4.12.2 REA0 TOR BUILDING PURGE AIR TREATMENT SYSTEM Acolicability: Applies to the reactor building purge air treatment system and associated components (Reference 1).

Obiective:

To verify that this system and associated components will be able to perform its design functions.

Specification 4.12.2.1 At least once per refueling interval, it shall be demonstrated that the pressure dro) across the combined HEPA filters and charcoal adsorber ban (s is less than 6 inches of water at system design flow rate ( 10%).

4.12.2.2 a.

The tests and sample analysis required by Specification 3.15.2.2, shall be performed initially, once per refueling interval, or within 30 days prior to the movement of irradiated fuel in containment and following significant painting, steam, fire, or chemical release in any ventilation zone mmmunicating with the system that could contaminate the HEPA filters or charcoal adsorbers, b.

D0P testing shall be performed after each complete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing which could affect HEPA frame bypass leakage, c.

Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakage, d.

The DOP and halogenated hydrocarbon testing shall be performed at the maximum available flow considering physical restrictions, i.e., purge valve position, and gaseous radioactive release criteria, e.

Each refueling, AH-E7A&B shall be shown to operate within i 5000 cfm of design flow (50,000 cfm) with purge valves fully open.

4.12.2.3 An air distribution test shall be performed on the HEPA filter bank initially and after any maintenance or testing that could affect the air distribution within the system.

The air distribution across the HEPA filter bank shall be uniform within 20%. The test shall be performed at 50,000 cfm (110%)

flow rate with purge valves' fully open.

i 4-55b Amendment No. 55, ES, Jpp, H P, 157

.s 4.17 SHOCK SUPPRESSORS (SNUBBERS)

SURVEILLANCE RE0VIREMENTS 4.17.1 Each snubber shall be demonstrated OPERABLE by performance of the following inspection program.

a.

Snubber Tvoes As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of

capacity, b.

Visual Insoections Snubbers are categor; zed as inaccessible or accessible during reactor operation and may be treated independently. The TM1-1 Manager, Radiological Controls, will ensure that a review is performed for ALARA considerations on all snubbers which are located in radiation areas for the determination of their accessibility.

This review shall be in accordance with the recommendations of Regulatory Guides 0.8 and 8.10.

The determination shall be based upon the known or projected radiation levels at each snubber location which would render the area inaccessible during reactor operation and based upon the expected time to perform the visual-inspection. -Snubbers may also be determined to be inaccessible because of their physical location due to an existing industrial safety hazard at the specific snubber location.

This determination shall be reviewed and approved by the Supervisor of Safety and Health.

Snubbers accessible during reactor operation shall be inspected in accordance with the schedule stated below.

Snubbers scheduled for inspection that are inaccessible during reactor operation because of physical location or radiation levels shall be inspected during the next reactor shutdown greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> where access is restored

  • unless previously inspected in accordance with the schedule stated below.

Visual inspections shall include all safety related snubbers and shall be performed in accordance with the following st.hedule:

No. Inoperable Snubbers of Each Subsequent Visual Tvoe per Insnectiqn Period 10.soection period **#

0 24 months 25%

l 1

16 months i 25%

2 6 months i 25%

3, 4 124 days i 25%

5,6,7 62 days i 25%

8.r more 31 days 1 25%

Snubbers may continue to be inaccessible during reactor shutdown greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (e.g. if purging of the reactor building is not permitted).

_The inspection interval for each type of snubber shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found.

The provisions of Table 1.2 are not applichble. 60 Amendmen.t No. 79, Jpp, 110

__________J

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