ML18033A656

Proposed Tech Spec Tables 4.1.B,4.2.B & 4.2.F Re Calibr Frequencies

ML18033A656
Person / Time
Site:	Browns Ferry
Issue date:	02/24/1989
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18033A654	List: ML18033A653 ML18033A656
References
NUDOCS 8903080159
Download: ML18033A656 (20)

Text

Enclosure 1 Propo ed Technical Specifications Revi "ions Brows Ferry Nuclear Plant Unit 2 (TVA BFN TS 263) 89030SOi59 890224 PDFi ADOCK 05000260 P PDC

I 0'

TABLE 4.1.8 REACTOR PROTECTION SYSTEH (SCRAM) INSTRUMENT CALIBRATION HINIHUH CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CIIANNELS Instrwnent Channel Grou 1 Calibration Minimum Fre uenc 2 IRM Iligh Flux Comparison to APRH on Controlled Note (4)

Startups (6)

APRH lligh Flux Output Signal Ileat Balance Once/1 Days Flow Bias Siijnai Calibrate Flow Bias Signal (7) Once/Operating Cycle LPRH Signal TIP Systen Traverse (8) Every 1000 Effective Full Power Hours .

lligh Reactor Pressure Standard Pressure Source Once/6 Honths (9) tPIS-3-22 AAp BBp Cp D) lligh Drywell Pressure Standard Pressure Source Once/18 Honths (9)

(PIS-64-56 A-D)

Reactor Low bhter Level Pressure Standard Once/10 Honths (9)

(LIS-3-203 A-D) lligh 4hter Level in Scram Discharge Volume Float Switches (LS-8545-C-F) Calibrated Mater Column Once/10 Months Electronic Level Switches (I.S-85-45 A, B, G, ll) Calibrated Mater Colunm Once/18 Honths (9)

Hain Steam Line Isolation Valve Closure Note (5) Note (5)

Hain Steam Line Iligh Radiation Standard Current Source (3) Every3 Honths Turbine First Stage Pressure Permissive (PIS-1-81 AEB, P 15-1-91 AEB) Standard Pressure Source . Once/18 Months (9)

Turbine Stop Valve Closure Note (5) Note (5)

I Turbine Control Valve Fast Closure on Turbine Trip Standard Pressure Source Once/Operating Cycle Low Scram Pilot Air Ileader Pressure (PS 85-35 Al, Standard Pressure Source Once/18 Honths A2, Bl, 6 B2)

BFN-Unit 2

I TABLE 3.2.B ltlSTRUHENTATION TINT INITIATES OR CONTROLS TllE CORE AND CONTAINMENT COOLING SYSTEHS Hininun No.

Operable Per T~ri Ss i Function Tri Level Settin Action Remarks Instrument Channel > 470" above vessel zero. A l. Below trip setting initiated Reactor Low bhter Level Itpcl.

(LIS-3-58A-D)

Instrunient Channel > 470" above vessel zero. A 1. Hultiplier relays initiate Reactor Low bhter Level RCIC.

(LIS-3-58A-0) lnstrunient Channel > 378" above vessel zero. A l. Below trip setting initiates Reactor Low bhter Level CSS.

(LS-3-58A-D)

Hultiplier relays initiate LPCI.

2. Hultiplier relay From CSS initiates accident signal (15).

2(16) Instrument Channel > 378" above vessel zero. A 1. Below trip settings, in Reactor Low bhter Level conjunction with drywell (LS-3-58A-0) high pressure, low water level permissive, 120 sec.

delay timer and CSS or RllR puny running, initiates ADS.

1(16) Instrunient Channel > 544" above vessel zero. A 1. Below trip setting permissive Reactor Low bhter Level For initiating signals on ADS.

Permissive (LIS-3-184, 185)

Instrument, Channel > 312 5/16" above vessel zero. A l. Below trip setting prevents Reactor Low bhter Level T2/3 core height) inadvertent operation oF (LISH-52 and LIS-3-62A) containment spray during accident condition.

< The autoniatic initiation capability of this instrument channel is not required to be OPERABLE awhile the Reactor Vessel water level nenitoring nndification is being perFormed. Hanual initiation capability of the associated system wi 11 be available during that time the automatic initiation logic is out-of-service.

BFN-Vnit 2

TABLE 3.2.B (Continued)

Hinimum Wo.

Operable Per

~Tri Ss i Function Tri Level Settin Action Remarks Instrument Channel- 1< p<2.5 psig l. Below trip setting. prevents Drywell High Pressure inadvertent operation oF (PIS-64-58 E-H) containment spray during accident conditions.

Instrument Channel- < 2.5 psig l. Above trip setting in con-Drywell High Pressure junction with low reactor (PIS-64-58 A-D) pressure initiates CSS.

Hultiplier relays initiate HPCI.

2. Hultiplier relay from CSS initiates accident signal. ( 15)

Instrunient Channel- > 470" above vessel zero l. Below trip setting trips Reactor Low Mater Level recirculation pumps.

(LS-3-56A-0)

Instrument Channel < 1120 psig l. Above trip setting trips Reactor High Pressure recirculation pumps.

(PIS-3-204A-D)

Instrument Channel- < 2.5 psig l. Above trip setting in Drywell High Pressure conjunction with low (PIS-64-58A-D) reactor pressure initiates LPCI.

2(16) Instrument Channel- < 2.5 psig l. Above trip setting, in Drywell High Pressure conjunction with low reactor (PIS-64-5IAW) water level, drywcll high pressure, 120 sec. delay timer and CSS or RIIR pump running, initiates ADS.

BFII-Ilnit 2

TABLE 3.2.B (Continued)

H I ll i lMll Ho Operable Per T~ri S s 1) Function Tri Level Settin Action Remarks HPCI Trip System bus power H/A 1. Honitors availability of ~

nionitor power to logic systems.

RCIC Trip System bus power N/A 1. Honitors availability of nioni tor power to logic systems.

1(2) Instrument Channel > Elev. 551' l. Belo~ trip setting will Condensate Header Low open HPCI suction valves Level (LS-73-55A 4 B) to the suppression chaniber.

I(2) Instrument Channel- 7" above instrument zero A l. Above trip setting will open Suppression Chamber High HPCI suction valves to tlie Level suppression chamber.

2(2) Instrument Channel < 503" above vessel zero l. Above trip setting trips RCIC Reactor High Mater Level turbine.

(LIS-3-208A and LIS-3-200C)

Instrument Channel- < 450" H20 (7) l. Above trip setting isolates RCIC Turbine Steam Line RCIC system and trips RCIC High Flow turbine.

(PDIS-71-1A and B) 4(4) Instrument Channel- <2000F. 1 ~ Above trip setting isolates RCIC Steam Line Space RCIC system and trips RCIC High Temperature turbine.

3(2) Instrument Channel- >50 psig l. Below trip setting isolates RCIC Steam Supply RCIC system and trips RCIC Pressure Low turbine.

(PS 71-'IA-D) 3(2) Instrument Channel- <20 psig l. Above trip setting isolates RCIC Turbine Exhaust RCIC system and trips RCIC Diaphragm Pressure - High turbine.

(PS 71-11A-D)

BFH-Unit 2

TABLE 3.2.8 (Continued)

Hininvan Mo.

Operable Per T~ri Ss i Function Tri Level Settin Action Renarks 2(2) Instrument Channel <583" above vessel zero. l. Above trip setting trips HPCI Reactor High Mater Level turbine.

(LIS-3-20BB and LIS-3-2000)

Instrument Channel- <90 psi (7) l. Above trip setting isolates HPCI Turbine Steam Line HPCI system and trips HPCI High Flow turbine.

(PDIS-73-1A and 1B) 3(2) Instrument Channel- >100 psig 1. Below trip setting isolates HPCI Steam Supply HPCI system and trips HPCI Pressure - Low (PS 73-lA-D) turbine.

3(2) Instrument Channel- <20 psig l. Above trip setting isolates HPCI Turbine Exhaust HPCI system and trips HPCI Diaphrayn (PS 73-20A-D) turbine.

4(4) lns truant Channel - <200'F. 1 ~ Above trip setting isolates HPCI Steam Line Space High HPCI system and trips HPCI Tenyerature turbine.

Core Spray System Logic H/A l. Includes testing auto initiation inhibit to Core Spray Systems in other units.

RCIC System (Initiating) H/A l. Includes Group 7 valves.

Logic Refer to Table 3.7.A for list of valves.

RCIC System (Isolation) W/A 1. Includes Group 5 valves.

Logic Refer to Table 3.7.A for list of valves.

1 (16) ADS Logic W/A 1 RHR (LPCI) System N/A (Initiation)

BFM-Unit 2

TABLE 4.2.8 SURVEILUQICE REQUIREMEtlTS FOR INSTRUMEtJTAT ION THAT ItllTIATE OR COHTROL TllE CSCS Function Functional Test Calibration Instrument Check Instrument Channel (1) (27) Once/18 Honths (20) Once/day Reactor Low Mater Level (LIS-3-58A-D)

Instrunent Channel (1) (27) Once/18 Honths (20) Once/day Reactor Lou Mater Level (I ISA-104 8 105)

Instrument Channel (1) (27) Once/18 Honths (20) Once/day Reactor Lo~ Mater Level (LIS-3-52 4 62A)

Instrument Channel (1) (2I) Once/18 Honths (20) none Reactor Lou Mater Level (LS-3-56A-D)

Instrunmnt Channel (1) (27) Once/18 Honths (20) none Reactor lligh Pressure (P IS-3-204A-D)

Instrument Channel (1) (27) Once/10 Months (20) none Orwell Iligh Pressure (P I5-64-50E-ll)

Instrunv~nt Channel (1) (27) Once/10 Months (20) none Orwell Iligh Pressure (P IS-64-50A-D)

Instrument Channel (1) (2I) Once/18 Months (20) none Orywell lligh Pressure (P IS-64-57A-D)

Instrument Channel (1) (2I) Once/6 Honths (20) none Reactor Lou Pressure (P 15-3-74 SB, PS-3-74lQLB)

(PIS-60-95, PS-60-95)

(P I5-60-96, PS-68-96)

BFtl-Unit 2

TABLE 4.2.8 (Continued)

SURYEILIJQICE REI)UIREHEHTS FOR IHSTRUHCHTATION THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check Instrument Channel- once/3 months none RIIR Pump Discharge Pressure Instrument Channel once/3 months none Core Spray PIuIy Discharge Pressure Core Spray Sparger to RPV d/p once/3 months once/day Trip System Bus Power Honitor once/operating Cycle H/A none InstrunIent Channel- once/3 months none Condensate Header Lov Level (LS-13-56A, B)

Instrument Channel once/3 months none Suppression Chan1ber High Level Instrument Channel once/3 ninths once/day Reactor High Mater Level Instrument Channel- once/3 months none RCIC Turbine Steam Line High Floe Instrument CIIannel- once/3 months none RCIC Steam Line Space High TenT1erature Instrenent Channel- once/31 days once/18 months none RCIC Steam Supply Low Pressure Instrunv.nt Channel- once/31 days once/18 months , none RCIC Turbine Exhaust Diaphragm High Pressure BFH-Unit 2

TABLE 4.2.B (Continued)

SURVEILLANCE REIlUIREHEIITS FOR ItJSTRUYiEHTATION TIIAT INITIATE OR CONTROL TIIE CSCS Function Functional Test Calibration Instrument Check Instrument Channel- Once/3 months none IIPCI Turbine Steam Line lligh Flow Instrument Channel- Once/3 nenths none IIPCI Steam Line Space Itigh Ten@erat,ure Instrument Channel- once/31 days once/18 months none IIPCI Steam Supply Low Pressure Instrument Channel- once/31 days once/18 months none IIPCI Turbine Exhaust Diaphragm Itigh Pressure Core Spray System Logic once/18 months (6) tJ/A RCIC System (Initiating) Logic once/18 months H/A N/A RCIC System (Isolation) Logic once/18 months (6) H/A IIPCI System (Initiating) Logic once/18 months (6)

IIPCI System (Isolation) Logic once/18 months (6) N/A AOS Logic once/18 months (6) H/A LPCI (Initiating) Logic once/18 months (6) tt/A LPCI (Containnent Spray) Logic once/18 months (6)

Core Spray System Auto Initiation once/18 months (7) N/A Inhibit (Core Spray Auto Initiation)

LPCI Auto Initiation Inhibit once/18 months (7) N/A H/A (LPCI Auto Initiation)

BFH-Unit 2

TABLE 4.2.F HIHIHUR TEST AHD CALIBRATIOH FREQUENCY FOR SURVEILLANCE INSTRUHEHTATIOH Instrument Channel Calibration Fre uenc Instrument Check

1) Reactor Mater Level Once/6 nenths Each Shift

( LI-3-SSNR)

2) Reactor Pressure Once/6 months Each Shift (PI-3-74@as)

3) D~eli Pressure Once/6 months Each Shift (Pl-64-678)"and XR-64-50

4) Dryuell Temperature Once/6 months Each Shift (TI-64-52AB) and XR-64-50

5) Suppression Chamber Air Tenyerature Once/6 months Each Shift (XR-64-52)

8) Control Rod Position N/A Each Shift

9) Neutron Ronitoring (2) Each Shift

10) Orwell Pressure (PS-64-678) Once/6 months H/A

11) Dryuell Pressure (PIS-64-58A) Once/6 months H/A

12) Orwell Tenyerature (TS-64-52A) Once/6 months N/A

13) Tier (IS-64-67A) Once/6 months H/A

14) CAD Tank Level Once/6 nenths Once/day

15) Containment Atnesphere Honitors Once/6 months Once/day BFH-Unit 2

l Hnclosure 2 Description and Justification Browns Perry Nuclear Plant Unit 2 Reason Eox; Chan e This technical pecification change corrects Browns Fexry unit 2 technical specification tables 4.1.B, 4.2.B, and 4.2.F for calibration frequencies and includes administrative changes to instrument numbers.

Instrument loops that contain transmitters manuEactured by Tobar Inc. will only permit a 6-month calibration frequency. Instrument numbers in the tables are added or corx.ected to provide a concise set of technical specifications.

Instrument checks for (4) instrument channels in table 4.2.B that have no remote ox; local indication are deleted.

Descri tion and Justification Calibration Frequency Changes:

In general surveillance fx.equencies are based on industry accepted practice and engineering judgment considexing the conditions required to perform a given test, the ease of performing the test and the likelihood oE a change in the .ystem/component tatus. Instrumentation calibration fx.equencies consist oE an optimum selection of time vex.sus drift. Setpoint scaling calculations are performed to provide assurance there is adequate margin to account Eor all inaccuracies in tho instrument loop between the requix;ed trip setpoint and the limiting safety "ystem settings.

These changes to the calibration frequencies are required to support the results of the setpoint and scaling calculations for various instrument loops.

The specific changes are illustrated and justified below:

Table 4.1.B Instrument Hxistin Pre uenc Pro osed Chan e liigh Reactor Pressux;e Once/18 months Once/6 months (pg 3.1/4.1-11) 0358y

Table 4.2.8

'I 1n's trument Hxistin Fre uenc Pro osed Chan e Reactor low pressure Once/18 months Once/6 months (pg 3.2/4.2-44)

These instrument loops contain tran. mittevs manufactured by Tobar inc. The tvansmittevs only permit a 6-month calibvation frequency.

Table 4.2.F Reactor Pressure Once/12 months Once/6 months (pg, 3.2/4.2-54)

Thi: loop contains tvansmitters manufactured by Tobar Inc. These transmitters only permit a 6-month calibvation frequency.

'Note: DFH technical specification definition "Surveillance" permits a maximum allowable extension not to exceed 25 percent of the surveillance interval. This allowable extension of the surveillance interval was considered in defining the calibration frequencies.

Additions/change to in"trumentation numbers Table 3.2.8 Instrument Rxistin Number Pro osed Chan e Reactor low water level (LIS-3-58A-D) (LS-3-58A-D)

(pg 3.2/4.2-14i)

Note: This change pr.oposed for 2 places on pg 3.2/4.2-14.

Reactor low water level (I IS-3-62) (LIS-3-62A)

(pg 3.2/4.2-14)

Drywall high pressuz.e (PS-64-58A-D) (PIS-64-58A-D)

(pg 3.2/4.2-15)

Reactor: l.ow water level (LIS-3-56A-D) (LS-3-56A-D)

(pg 3.2/4.2-15)

Reactor high water level (LIS-3-208A and (pg 3.2/4.2-18) LIS-3-208C)

RCIC turbine steam line (PDXS-71-lA and 18) high flow

( pg 3. 2/4 . 2-18)

Reactor high water level (LIS-3-2088 and (pg 3.2/4.2-19) LIS-3-208D) 14PCI turbine steam line (PDIS-73-1A and 18) high flow (pg 3.2/4.2-19)

Table 4. 2.8 Reactor low water level (LIS-3-62) (LIS-3-62A)

(pg 3.2/4.2-44)

Reactor low water level (LIS-3-56A.-D) (LS-3-56A-D)

(pg 3.2/4,2-44)

These changes are administr.'ativo in natur:e and do not change the function, setting, or calibration interval of any of the listed instr:uments. They are included in the technical specifications for completeness.

Deletion of instrument ch k for llPCI/RCIC instrument chan ls:

Table 4.2.9 Instrument Fxistin T/S Pro osed chan e RCIC steam supply low Once/day none pressure (pg 3.2/4.2-46)

RCIC turbine exhaust Once/day none diaphragm high pressure (pg 3.2/4.'2-46)

RPCI turbine steam line Once/day none high flow (pg 3.2/4.2-47) lkPCI turbine exhaust, Once/day none diaphragm high pressure (pg 3.2/4.2-47)

These instrument channels consist of pres ure switches (PS71-1A-D, PS71-11A-D, PS73-1A-D, PS73-20A-D) that have no indication. An instrument check is a qualitative determination of acceptable behavior by observation of the instrument during operation. These pressure switches have no indication function. The functional test of the instrumentation which verifies operability including the alarm and trip functions is performed once/31 days.

Enclosure 3 Determination of Ho Significant )lazar.ds Consideration Brown" Ferry Nuclear Plant Vnit 2 Descei tion This technical specification change revises the calibration feequencies and coeeects instr~ment numbers of various insteuments in Bx;owns Fevx.y unit 2 technical specification tables 4.1.B, 4.2.B, and 4.2.F. The instrument checks fov high peessux.e coolant injection (IlPCI) and x.eactoe cox.e isolation cooling (RCIC) system instrument channels are deleted fvom table 4.2.B.

Basis for Peo osed Ho Si nificant llazards Consideration Determination HRC has provided standaeds for determining whethev a significant hazaeds consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license involves no significant hazards considevations of Uxe facility in accordance with the proposed amendment would not (1) if operation involve a significant inceease in the peobability or consequences of an accident peeviously evaluated, (2) create the possibility of a new or diffeeent kind of accident from an accident previously evaluated, or (3) involve a ..ignificant eeduction in a margin of safety.

1. The proposed amendment does not involve a significant inceease in the peobability ox. consequences of an accident previously evaluated. Tho primary factor in setting the calibration intevvals is the drift of the teansmittees and teip units. TVA has performed setpoint scaling calculations that support the proposed change using manuEacturees reconxmended intevvals and indu..tey standard practices. This change does not involve a design change ov physical change to the plant. The x;evised surveillance fvequencies will not affect the consequences of an accident peeviously analyzed.

The reliability of the llPCI/RCIC diaphragm high pressuee, steam line flow and steam supply pressure insteuments ax.e adequately assueed by the perfonnance of Eunctional tests every 31 days.

Clarifications ov coevections of typogvaphical ereovs ave administrative changes which improve technical specification x;eliability and thevefoee can have no deteimontal impact.

2. The peoposed change does not create the possibility of a new or diffevent kind of accident Eeom any accident previously evaluated because changing the technical.speciEications to x.'eflect diEfeeent calibration fvequencies does not affect oe change design operating limits or pvotective setpoints. No new ox different mode" of operation are allowed by those changes.

3. The proposed change .does not involve a significant reduction in a margin of afety because in no instance will these changes affect the technical specification safety limits. These changes have no affect on the instrument setpoints. All parameters will continue to be monitored as currently required.

Since the application for amendment involves a proposed change that is encompa., ed by the criteria for: which no significant hazards consideration exist, TVA has made a proposed determination that the application involves no significant hazards consideration.

tg

)