Text

Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively, Extending APRM Flow Bias Instrumentation Surveillance Interval from 18 Months to 24 Months
	ML20217M796
Person / Time
Site:	Peach Bottom
Issue date:	08/19/1997
From:	Stolz J; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20217M774	List: ML20217M770; ML20217M796; ML20217M800;
References
	NUDOCS 9708250300
	Download: ML20217M796 (38)
	v • d • e

______________________ ___-__ - _ _

patog g t UNITED STATES s* j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3086H001

'4 '

9 . . . . . ,o PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DLLMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 j

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.219 License No. DPR-44

1. The Nuclear Regulatory Commission (the Commission) has found that: 1 A.

The application for amendment by PECO Energy Company, et. al. (the licensee) dated March 31, 1997, as supplemented by letter dated June 25, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.

5. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authoriz9d by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

9708250300 970819 PDR P

ADOCK 05000277 PDR

- 2~-

(2) Technical Soecifications The Technical Specifications contained in Ap)endices A and B, as revised through Amendment No. 219 , are here>y incorporated in the license. PECO Energy Company shall operate the facility in accordance -

with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 6

J n . Stolz, Director '

ect Directorate I ision of Reactor Projects - I/II l Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 19, 1997 1

e o ATTACHMENT TO LICENSE AMENDMENT NO.91o FACILITY OPERATINC- l_ICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Insert 3.3-5 3.3-5 3.3-6 3.3-6 3.3-7 3.3-7 B 3.3-23 thru 35 B 3.3-23 thru 35 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE I FREQUENCY SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. 92 days

-SR 3.3.1.1.10 ------------------NOTE-------------------

Radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days l

SR 3.3.1.1.11 .-----......------NOTES--- -..-------..--

1. Neutron detectors are excluded.

2. Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION. 184 days i

SR 3.3.1.1.12 ------------------NOTES------------------

1. Neutron detectors are excluded.

2. For Function 2.a. not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE-2.

3. APRM flow units and associated flow transmitters are excluded.

Perform CHANNEL CALIBRATION. 18 months (continued)

PBAPS UNIT 2 3.3-5 AmendmentNo.j{g, 219

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.13 Verify Turbine Stop_ Valve-Closure and 24 months Turbine Control Valve Fast Closure, Trip 011 Pressure-Low Functions are not bypassed when THERMAL POWER is a 30% RTP.

SR -3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.15 Perform CHANNEL CALIBRATION. 24 months l

l-SR 3.3.1.1.16 Calibrate each radiation detector. 24 months SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.

SR 3.3.1.1.19 Calibrate APRM flow units and associated 24 months flow transmitters.

PBAPS UNIT 2 3.3-6 Amendment No. .

h_s,.i. . . .,-,, , ' -.- -- ' - '

RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (pope 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDifl0NS MODES DE RE00lkED REFERENCED OTHER CHANNELS PROM SPECIFIED PER falP RE00lRED SURVEILLANCE FUNCfl0N ALLOWASLE CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Interneciate Range Monttore

e. boutron Ftus - Nish 2 3 G SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.5 futt scate sa 3.3.1.1.6 ER 3.3.1.1.11 BR 3.3.1.1.17 sa 3.3.1.1.18 5(*) 3 N SR 3.3.1.1.1 s 120/125 st 3.3.1.1.4 divisions of sa 3.3.1.1.11 full scale SR 3.3.1.1.17 st 3.3.1.1.18

b. Inop 2 3 G SR 3.3.1.1.3 UA SR 3.3.1.1.17 5(*) 3 N SR 3.3.1.1.4 NA SR 3.3.1.1.17

2. Aversee Power Range Monttors

a. Start @ Migh Flum 2 2 scram C SR 3.3.1.1.1 s 15.0% RTP SR 3.3.1.1.3 SR 3.3.1.1.6 SR 3.3.1.1.8 tt 3.3.1.1.12 la 3.3.1.1.17 SR 3.3.1.1.18

b. Flow Blased Nigh 1 2 Scram F Sa 3.3.1.1.1 s 0.66 W SR 3.3.1.1.2 + 63.9E RTPID)

SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 sa 3.3.1.1.17

l SR 3.3.1.1.18 SR 3.3.1.1.19

c. m Clasp 1 2 F SR 3.3.1.1.1 s 118.0% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 ER 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18

d. Downscete 1 2 F SR 3.3.1.1.8 1 2.5X RTP SR 3.3.1.1.9 84 3.3.1.1.17

e. Inap 1,2 2 G 58 3.3.1.1.8 #A SR 3.3.1.1.9 st 3.3.1.1.17 (continued) to) With any control rod withdrawn from a core cell contelning one or more fuel assenblies.

(b) 0.66 W + 63.91 0.66 AW RTP when reset for einste loop operation per LCO 3.4.1, anecircutetton Loops operating."

PSAPS 'JNIT 2 3.3*7 W t No.219

RPS Instrumentation B 3.3.1.1 BASES APPLICABLE 14.

SAFETY ANALYSES, RPS Channel Test Switch (continued)

LCO, and RPS Functions, described in Reference 9, were not affected APPLICABillTY by the difference in configuration, since each automatic RPS channel has a test switch which is functionally the same as the manual scram switches in the generic model. As such, the RPS Channel Test Switches are retained in the Technical Specifications. '

l There is no Allowable Value for this Function since the channels are mechanically actuated based solely on the position of the switches.

Four channels of RPS Channel Test Switch with two channels in each trip system arranged in a one-out-of-two logic are available and required to be OPERABLE in MODES I and 2, and in MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, since these are the MODES and other specified conditions when control rods are withdrawn.

ACTIONS A Note has been provided to modify the ACTIONS related to l

RPS instrumentation channels. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RPS instrumentation channels provide appropriate com)ensatory measures for separate inoperable channels. As suc1, a Note has been provided that allows separate Condition entry for each inoperable RPS instrumentation channel.

A.1 and A.2 Because of the diversity of sensors available to provide.

trip signals and the redundancy of the RPS design, an allowable out of service time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months has been shown to be acceptable (Ref. 9) to permit restoration of any inoperable channel to OPERABLE status. However, this out of service time is only acceptable provided the associated (continued)

PBAPS UNIT 2 B 3.3-23 Revision No.

Amendment No. 219

RPS Instrumentation B 3.3.1.1 BASES ACTIONS A.1 and A.2 (continued)

Function's inoperable channel is in one trip system and the Function still maintains RPS trip capabilit Required Actions B.1, B.2, and C.1 Bases).Ify the(refer to ino>erable channel cannot be restored to OPERABLE status wit 11n the allowable out of service time, the channel or the associated trip system must be placed in the tripped condition per Required Actions A.1 and A.2. Placing the H inoperable channel in trip

-trip) would conservatively c(ompensate for the inoperability,or th i restore capability to accommodate a single failure, and allow operation to continue. Alternatively, if-it is not desired to place the channel (or trip system) in trip (e.g.,

" as in the case where placing the inoperable channel in trip would result in a full scram), Condition D must be entered and its Required Action taken.

4 B.1 and B.2 Condition B exists when, for any one or more Functions, at least one required channel is inoperable in each trip system. In this condition, provided at least-one channel per trip system is OPERABLE, the RPS still maintains trip.

capability for that Function, but cannot accommodate a single failure in either trip system.

Required Actions B.1 and B.2 limit the time the RPS scram logic, for any Function, would not accommodate single failure'in both trip systems (e.g., one-out-of-one and one-out-of-one arrangement for a typical four channel Function). The reduced reliability of this--logic

-arrangement was not evaluated in Reference 9 for the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time. - Within the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the associated Function will have all required channels OPERABLE or in trip (or any combination) in one trip system.

Completing one of these Required Actions restores RPS to a reliability level equivalent to that evaluated in Reference 9, which justified a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowable out of

service time as presented in Condition A. The trip system in the more ' degraded state should be placed in trip or, niternatively, all the. inoperable channels in that trip system should be placed in-trip (e.g., a trip system with (continued)

PSAPS UNIT 2 B 3.3-24 Revision No.

Amendment No. 219

J RPS Instrumentation B 3.3.1.1 i

BASES ACTIONS B.1 and B.2 (continued) two inoperable channels could be in a more degraded state than a trip system with four inoperable channels if the two inoperable channels are in the same Function while the four inoperable channels are all in different Functions). The decision of which trip system is in the more degraded state should be based on prudent judgment and take into account current plant conditions (i.e., what MODE the plant is in),

if this action would result in a scram, it is permissible-to place the other-trip system or its inoperable channels in '

trip.

The 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Comaletion Time is judged acceptable based on the remaining capasility to trip, the diversity of the sensors available to provide the trip signals, the low probability of extensive numbers of inoperabilities affecting all diverse Functions, and the low probability of an event requiring the initiation of a scram.

Alternately, if it is not desired to place the inoperable channels where plac(or oneinoperable ing the trip system) in tripor(e.g.,

channel as in the associated tripcese system in trip would result in & scram, Condition D aust be entered and its Required Action teken.

L.d Required Action C.) is intendeel to ensure that appropriate actions are taken if multiple, inoperable, untripped-channels within the same trip system for the same Function result in an automatic Function, or two or more manual Functions, not-maintaining RPS trip capability. A Function is considered to be maintaining RPS trip capability when sufficient channels are OPERABLE or in trip -(or the associated trip system is in trip), such that both trip systems will generate a trip signal from the given Function -

on a valid signal. For the typical Function with one-out-of-two taken twice logic and the IRM and APRM Functions.

this would require both trip systems-to have one channel OPERABLE or in trip (or the associated trip system in trip).

For Function 5 (Main Steam Isolation Valve-Closure), this would require both trip systems to have each channel associated with the MSIVs in three main steam lines (ncit necessarily the-same main steam lines for both trip systems)

(continued)

PBAPS UNIT 2 B 3.3-25 Revision No.

=mamant No. 219

RPS Instrumentation B 3.3.1.1

{

BASES ACTIONS L1 (continued)

OPERABLE or in trip (or the associated trip system in trip).

For Function 8 (Turbine Stop Valve-Closure), this would require both trip systems to have three channels, each OPERABLE or in trip (or the associated trip system in trip).

For Functions 12 (Reactor Mode Switch-Shutdown Position) and 13 (Manual Scram), this would require both trip systems to have one channel, each OPERABLE or in trip (or the associated trip system in trip).

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. The I hour Completion Time is acceptable bectise it minimizes risk while allowing time for restoration or tripping of channels, i Dd Required Action D.1 directs entry into the appropriate Condition referenced in Table 3.3.1.1-1. The applicable condition specified in the Table is Function and MODE or other specified condition dependent and may change as the Required Action of a previous Condition is completed. Each time an inoperable channel has not met any Required Action of Condition A, B, or C and the associated Completion Time has expired, Condition D will be entered for that channel and provides for transfer to the appropriate subsequent Condition.

E.1. F.1. and G.1 If the channel (s) is not restored to OPERABLE status or placed in trip (or the associated trip system placed in trip) within the allowed Completion Time, the plant must be placed in a MODE or other specified condition in which the LCO does not apply. The allowed Completion Times are reasonable, based on operating experience, to reach the specified condition from full power conditions in an orderly

- manner and without challenging plant systems. In addition.

the Completion Time of Required Action E.1 is consistent with the Completion Time provided in LCO 3.2.2, " MINIMUM CRITICAL POWER RATIO (MCPR)."

(continued)

PBAPS UNIT 2 B 3.3-26 Revision No.

Amendment No. 219

RPS Instrumentation B 3.3.1.1 i

i l

BASES ACTIONS lid (continued)

If the channel (s I placed in trip (o)r the associated trip system placed inis not resto trip place)d in a MODE or other specified condition in which thawith Lt0 does not apply. This is done by immediately initiating action to fully insert all insertable control rods in core cells containing one or more fuel assemblies. Control rods in core cells containing no fuel assemblies do not affect the reactivity of the core and are, therefore, not required to be inserted. Action must continue until all insertable control rods in core cells containing one or more fuel assemblies are fully inserted.

SURVEILLANCE As noted at the beginning of the SRs, the SRs for each RPS REQUIREMENTS instrumentation Function are located in the SRs column of Table 3.3.1.1-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , provided the associated Function maintains RPS trip capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Ref. 9 time required to perform channel) Surveillance. assumption of the averag That analysis demonstrated that the 6 hour-testing allowance does not significantly reduce the probability that the RPS will trip when necessary.

SR 3.3.1.1.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter-indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of (continued)

PBAPS UNIT 2 B 3.3-27 Revision No.

Amendment No. 219

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.1 (continued)

REQUIREMENTS excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is- key to verifying the instrumentation continues to operate properly between each CHANNEL CAllBRAT10N.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indicad on and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.1.1.2 To ensure that the APRMs are accurttely indicating the true core average power, the APRMs are calibrated to the reactor power calculated from a heat balance. The Frequency of once per 7 days is based on minor changes in LPRM sensitivity, which could affect the APRM reading between performances of SR 3.3.1.1.8.

A restriction to satisfying this SR when < 25% RTP is provided that requires the SR 'a be met only at a 25% RTP because it is difficult to accurately maintain APRM indication of core THERMAL POWER consistent with a heat balance when < 25% RTP. At low power levels, a high degree of accuracy is unnecessary because uf the large, inherent margin to thermal limits (MCPR and APLHGR). At a 25% RTP, the Surveillance is required to have been satisfactorily performed within the last 7 days, in accordance with SR 3.0.2. A Note is provided which allows an increase in THERMAL POWER above 25% if the 7 day Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching or exceeding 25% RTP. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

(continued)

PBAPS UNIT 2 B 3.3-28 Revision No.

Amendment No. 219

.- , V RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.3 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required I channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be made I

consistent with the assumptions of the current plant specific setpoint methodology.

As noted, SR 3.3.3.3.3 is not required to be performed when entering MODE E from MODE 1, since testing of the MODE 2 required IRM and APRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads, or movable links. This allows entry into MODE 2 if the 7 day Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2 from MODE 1.

i Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

A Frequency of 7 days provides an acceptable level of system l

average unavailability over the Frequency interval and is based on reliability analysis (Ref. 9).

SR 3.3.1.1.4 t

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A Frequency of 7 days provides an acceptable level of system average availability over the Frequency and is based on the reliability analysis of References 9 and 10. (The RPS Channel Test Switch Function's CHANNEL FUNCTIONAL TEST Frequency was credited in the analysis to extend many automatic scram Functions' Frequencies.)-

SR 3.3.1.1.5 and SR 3.3.1.1.6 These Surveillances are established to ensure that no gaps i

in neutron flux indication exist from suberitical-to power operation for monitoring core reactivity status.

The overlap between SRMs and IRMs is required to be demonstrated to ensure that reactor power will not be increased into a neutron flux region without adequate indication. This is required prior to withdrawing SRMs from the fully inserted position since indication is being (continued)

PBAPS UNIT 2 B 3.3-29 Revision No.

Amendment No. 219

RPS Instrumentation B 3.3.1.1

{

BASES SURVEILLANCE SR REQUIREMENTS 3.3.1.1.5 and SR 3.3.1.1.6 (continued) transitioned from the SRMs to the IRMs.

The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overla) is not maintained. Overlap between IRMs and APRMs exists wien sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE I and MODE 2 can be made without either APRM downscale rod block or IRM upscale rod block. Overlap oetween SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are reading on-scale and increasing prior to reaching the SRM's maximum indication. Continued overlap can be achieved by withdrawing SRMs to an intermediate position to allow continued rod withdrawls.

As noted, SR 3.3.1.1.6 is only required to be met during entry into MODE 2 from MODE 1. That is, after the overlap requirement has been met and indication has transitioned to the IRMs, maintaining overlap is not required (APRMs may be reading downscale once in MODE 2).

If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the .ppropriate channel (s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.

A Frequency of 7 days is reasonable based on engineering judgment and the reliability of the IRMs and APRMs.

SR 3.3.1.1.7 The Average Power Range Monitor Flow Biased High Scram Functiu uses the recirculation loop drive flows to vary the trip setpoint. This SR ensures that the total loop drive flow signals from the flow units used to vary the setpoint is appro)riately compared to a valid core flow signal to verify tie flow signal trip setpoint and therefore, the APRM Function accurately reflects the req,uired setpoint as a function of flow. If the flow unit signal is not within the appropriate flow limit, the affected APRMs that receive an (continued)

PBAPS UNIT 2 B 3.3-30 Revision No.

Amendment No. 219

s .

RPS Instrumentation B 3 3.1.1 1

BASES SURVEILLANCE SR 3.3.1.1.7(continued)

REQUIREMENTS input from t,ie inoptrable flow unit must be declared inoperable.

t The Frequency of 31 da

, operating experience, and ys is the based on engineering reliability of this judgement, instrumentation.

SR 3.3.1.1.8 I LPRM gain settings are determined from the local flux l

profiles measured by the Traversing Incore Probe (TIP)

System. This establishes the relative local flux profile for appropriate representative input to the APRM System.

l The 1000 MWO/T Frequency is based on operating experience l l with LPRM sensitivity changes. I SR 3.3.1.1.9 and SR 3.3.1.1.14 A CHANNEL FUNCTIONAL TEST is performw a each required channel to ensure that the entire channel will perfern the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant s)ecific setpoint methodology. For Function 5, 7 and 8 ciannels, verification that the trip settings are,less than or equal to the specified Allowable Value during the CHANNEL FUNCTIONAL TEST is not recuired since the channels consist of mechanical switches anc are not subject to drift. In addition, Function 5 and 7 instruments are not accessible while the unit is operating at power due to high radiation and the installed indication instrumentation does not arovide accurate indication of the trip setting. For the

unction 9 channels, verification that the trip settings are less than or equal to the specified Allowable Value during the CHANNEL FUNCTIONAL TEST is not required since the instruments are not accessible while the unit is operating at power due to high radiation and the installed indication instrumentation does not provided accurate indication of the trip setting. Walver of these verifications for the above functions is considered acceptable since the magnitude of drift astaed in the setpoint calculation is based on a 24 month cal k ation interval. The 92 day Frequency of SR 3.3.1.1.9 is based on the reliability analysis of Reference 9.

(continued 1 i

PBAPS UNIT 2 8 3.3-31 Revision No.

Amendment No. 219

RPS Instrumentation 5 3.3.1.1 BASES SURVEILLANCE 1R 3.3.1.1.R and SR 3.3.1.1.14 (continued)

REQUIREMENTS The 24 month Frequency is based on the need to perfom this Surveillance under the conditions that apply during a plant outage and the potentt 1 for an unplanned transient if the Surveillance were pertomed with the reactor at power.

Operating experience has shown that these components will pass the Surveillance when performed at the 24 month Frequency.

IR 3.3.1.L.10. 1R 3.3. . : . L1. 4R 3 . 3 .1.1.12., i i 1R 3.3. .'.15, and SR .h.3 .1. L6 A CHANNEL Call 8 RAT 10N is a complete check of the instrument loop and the sensor. This test verifies that the channel: '

-responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the current plant specific setpoint methodology. SR 3.3.1.1.16, however, is only a calibration of the radiation detectors using a standard '

radiation source.

As noted for SR 3.3.1.1.11 and SR 3.3.1.1.12, neutron detectors are excluded from CHANNEL CALIBRATION because they are passive devices, witt, minimal drift and because of the difficulty of simulating a meaningful s\gnal. Changes in neutron detector sensitivity are compensated for by performing the 7 day calorimetric calibration

-(SR 3.3.1.1.2)and the 1000 MWD /T LPRM calibration against the TIPS SR 3.3.1.1.8 .

SRs 3.3.1(.1.11 and 3.3).1.1.12A second note is provided for that allows the APRM and IRM SRs to be performed within-It hours of entering MODE 2 from ,

MODE 1. Testing of the MODE 2 APRM and IRM Functions cannot be perfomed in MODE 1 without utilizing jumpers, lifted leads or movable links. This Note allows entry into MODE 2 from MODE 1, if the 184 day or 18 month Frequency is not met per SR 3.0.2. Twelve hours is based on operatinti experience and in consideration of providing a reasonable t<me in which to complete the SR. A third note is provided for SR 3.3.1.1.11 that excludes the APRM flow units and associated flow transmitters from this SR since the calibration requirement for these instruments is specified in SR-3.3.1.1.19. As noted for SR 3.3.1.1.10, radiation detectors are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is operating,-the radiation detectors are 0:entinuadi PBAPS UNIT-2 B 3.3-32 Revision No.

Amendment No. 219

~

RPS Instrumentation B 3.4.1.1 BASES SURVEILLANCE SR 3.3.1.1.10. SR 3.3.1.1.11. SR 3.3.1.1.12.

i REQUIREMENTS SR 3.3.1.1.15. and SR 3.3.1.1.16 (continued) generallyinahighradiationareatthesteamtunnel). This exclusion is acceptable because the radiation detectors are passive devices with minimal drift. The radiation detectors are ca,librated in accordance with SR 3.3.1.1.16 on a 24 month Frequency.

The 92 day Frequency of SR 3.3.1.1.10 is conservative with respect to the magnitude of equipment drift assumed in the setpoint analysis. The frequencies of SR 3.3.1.1.11 and SR 3.3.1.1.12 are based upon the assumption of a 184 day or an 18 month calibration interval, respectively, in the t determination of the magnitude of equipment drift in the setpoint analysis. The frequencies of SR 3.3.1.1.15 and SR 3.3.1.1.16 are based u)on the assumption of a 24 month calibration interval in tie determination of the magnitude of equipment drift in the applicable setpoint analysis.

SR 3.3.1.1.13 This SR ensures that scrams initiated from the Turbine Stop Valve-Closure and Turbine Control Valve Fast closure, Trip 011 Pressure-Low functions will not be inadvertently bypassed when THERMAL POWER is a 30% RTP. This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodologies are incorpor ted into the Allowable Value (s 29.4% RTP which is equivalent to s 138.4 psig as measured from turbine first stage pressure) and the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from turbine first stage pressurJ), the main turbine bypass valves must remain closed during the calibration at THERMAL POWER a 30% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e.,

the Functions are bypassed at a 30% RTP either due to open main turbine bypass valve (s) or other re,asons), then the affected Turbine Stop Valve-Closure and Turb4ne Control Valve Fast Closure. Trip 011 Pressure-Low Functions are considered inoperable. Alternatively, the by can be placed in the conservative conditionnonbypass).

(pass channelIf placed in the nonbypass condition, this SR is met and the channel is considered OPERABLE.

(continued)

PBAPS UNIT 2 B 3.3-33 Revision No.

Amendment No. 219

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR3.3.1.1.13(continued)

REQUIREMENTS I

! The frequency of 24 months is based on engineering judgment and reliability of the components.

SR 3.3.1.1.17 )

The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The functional testing of control rods (LCO 3.1.3), and SDV vent and drain valves overlaps this Surveillance to provide comple(LCO te testing3.1.8),

of the assumed safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during r. plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components will sass the Surveillance when performed at the 24 month Frequency, i SR 3.3.1.1.18 '

l This SR ensures that the individual channel response times are maintained less than or equal to the original design value. The RPS RESPONSE TIME acceptance criterion is included in Reference 11.

RPS RESPONSE TIME tests are conducted on a 24 month Frequency. The 24 month Frequency is consistent with the PBAPS refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

SR 3.3.1.1.19 The Average Power Range Monitor FI N Biased High Scram Function uses the recirculation loop drive flows to vary'the trip setpoint. This SR ensures that the flow unit instrumentation that supplies the recirculation flow signal to the APRM system responds to the measured recirculation flow within the necessary range and accuracy by use of a standard pressure source. CHANNEL CAllBRATION leaves the (continued)

PBAPS UNIT 2 8 3.3-34 Revision No.

Amendment No. 219

T------

RPS Instrumentation 8 3.3.1.1 i

8ASES SURVEILLANCE SR l REQUIREMENTS 3.3.1. M (continued) channel adjusted to account for instrument drifts between successive calibrations.

The Frequency of 24 months is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components will pass the Surveillance when performed at the 24 month Frequency.

REFERENCES 1. UFSAR, Section 7.2.

2. UFSAR, Chapter 14.

3. HEDO-23842, ' Continuous Control Rod Withdrawal in the Startup Range," April 18. 1978.

4. NEDC-32183P, ' Power Rerate Safety Analysis Report for Peach Bottom 2 & 3,' dated May 1993.

5. UFSAR, Section 14.6.2.

6. UFSAR, Section 14.5.4.

7. UFSAR, Section 14.5.1.

8. P. Check DischargeSystem (NRC)Safety letterEvaluation,'

to G. Lainas (NRC),1,"BWR December 1980. Scram

9. NEDO-30851-P-A , " Technical Specification Improvement Analyses for BWR Reactor Protection System,'

March 1988.

10. MDE-87-0485-1, " Technical Specification Improvement Analysis for the Reactor Protection System for Peach Bottom Atomic Power Station Units 2 and 3," October 1987.

11. UFSAR, Section 7.2.3.9.

PBAPS UNIT 2 8 3.3-35 Revision No. !

Amendment No. 219

_..9 ---

pm Cao yo It UNITED STATES g NUCLEAR REGULATORY COMMISSION

) WASHINGTON. D.C. 30264001

l l

PECO ENERGY COMPANY f"BLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY l

DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 222 License No. DPR-56

1. The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PECO Energy Com)any, et. al. (the licensee) dated March 31, 1997, as supplemented )y letter dated June 25, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1.

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C amended to read as(2) of Facility Operating License No. DPR-56 is hereby follows:

O e 2-(2) Technical Soecifications The Technical Specifications contained in A;pendices A and B as revised through Amendment No.222 , are here)y incorporated in the license. PECO shell operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION J 7.Stolz, Director P ect Directorate !

D vision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 19, 1997

l

. s ATTACHMENT TO LICENSE AMENDMENT NO.222 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following sages of the Appendix A Technical Specifications with i the enclosed pages. T1e revised areas are indicated by marginal lines.=

Remove Intert 3.3-5 3.3-5 3.3-6 3.3-6 3.3-7 3.3-7 B 3.3-23 thru 35 B 3.3-53 thru 35 I

l

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

^

SURVEILLANCE 1

FREQUENCY ,

i SR 3.3.1.1.9 Perforn CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.10 ------------------NOTE-------------------

Radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days l

SR 3.3.1.1.11 ------------------NOTES------------------

1. Neutron detectors are excluded.

2. Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION. 184 days

~

I SR 3.3.1.1.12 ------------------NOTES------------------

1. Neutron detectors are excluded.

2. For Function 2.a. not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

3. APRM flow units and associated flow transmitters are excluded.

Perform CHANNEL CALIBRATION. 18 months (continued)

PBAPS UNIT 3 3.3-5 Amendment No.2H ,

222

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.13 Verify Turbine Stop Valve-Closure and 24 months Turbine Control Valve Fast Closure. Trip 011 Pressure-Low Functions are not bypassed when THERMAL POWER is a 30% RTP.

SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.15 Perform CHANNEL CAllBRATION. 24 months SR 3.3.1.1.16 Calibrate each radiation detector. 24 months l

SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

[

SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.

SR 3.3.1.1.19 Calibrate APRM flow units and associated 24 months flow transmitters.

PBAPS UNIT 3 3.3-6 Amendnwnt No.2{j,

RPS Instrumentation 3.3.1.1 1eble 3.3.1.1 1 (pape 1 of 3)

Reactor Protection tystem Instrumentation APPLICABLE CONDill0kt 103)(8 08 titultt0 tifttikCED 01Mtt CNAhutL8 i80M SPitifitD Pit TRIP tt0Vltt0 SURVI!LLANCE ALLOWABLE l PWucil0N COWDIT10ml aflitN Attl0N D.1 AlgulttMEN18 VALut

! i, Inter < sie her e li.nitore

e. boutron fluu = With 2 3 0 et 3.3.1.1.1 s 120/125 at 3.3.1.1.3 divisions cf SR 3.3.1.1.5 futt scale 64 3.3.1.1.6 et 3.3.1.1.11 l

st 3.3.1.1.17 I SR 3.3.1.1.18 SI *I 3 N 84 3.3.1.1.1 s 120/12$

SR 3.3.1.1.4 divisions of st 3.3.1.1.11 futt scale SR 3.3.1.1.17 at 3.3.1.1.18

b. Insp 2 3 C M 3.3.1.1.3 hA et 3.3.1.1.17 5(*) 3 m et 3.3.1.1.4 NA 84 3.3.1.1.17

2. Ayerste Power tenpo 16coltore

e. ttert w Nith Fium 2 Screa 2 C lt 1.3.1.1.1 s 11.01 R1P 54 3.3.1.1.3 SR 3.3.1.1.6 st 3.3.1.1.8 SR 3.3.1.1.12 st 3.3.1.1.17 SR 3.3.1.1.18

b. Iiow I1esed Nith 1 2 4

Scram F SR 3.3.1.1.1 s 0.H W et 3.3.1.1.2 e 63.9% R1P(b)

SR 3.3.1.1.7 M 3.3 1.1.8 34 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.1T l st 3.3.1.1.13 SR 3.3.1.1.19 P. Scram Clmap 1 2 f SR 3.3.1.1.1 s 118.0E tiP l st 3.3.1.1.2 84 3.3.1.1.8 at 3.3.1.1.9 SR 3.3.1.1.12

$4 3.3.1.1.17 44 3.3.1.1.18

d. Domescale 1 2 F SR 3.3.1.1.8 t 2.51 tiP 82 3.3.1.1.9 82 3.5.1.1.17

e. Irep 1.2 2 4 84 3.3.1.1.8 hA 64 3.3.1.1.9

$t 3.3.1.1.17 (contirued)

(e) With any control rod withdrean free e core tell contelning one or more fuel essent>ttes.

(b) 0.M W e 63.91 0.66 &W R1P idien reset for einste loc, operation per LCO 3.4.1,

Recirculation Loops Operettrg.*

PBAPS UNIT 3 3.3-7 Amendment No.2T4, 222

RPS Instrumentation B 3.3.1.1 i

BASES APPLICABLE 14.

SAFETY ANALYSES, RPS Channel Test Switch (continued) J LCO, and RPS Functions, described in Reference 9, were not affected APPLICABILITY by the difference in configuration, since each automatic RPS channel has a test switch which is functionally the same as the manual scram switches in the generic model. As such, the RPS Channel Test Switches are retained in the Technical Specifications.

There is no Allowable Value for this Function since the channels are mechanically actuated based solely on the

, position of the switches.

l Four channels of RPS Channel Test Switch with two channels l

in each trip system arranged in a one-out-of-twc Icgic are l available and required to be OPERABLE in MODES 1 and 2, and in MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, since these are the MODES and other specified conditions when control rods are withdrawn.

ACTIONS A Note has been provided to modify the ACTIONS related to RPS instrumentation channels. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RPS instrumentation channels provide appropriate com)ensatory measures for separate inoperable channels. As suci, a Note has been provided that allows separate Condition entry for each inoperable RPS instrumentation channel.

A.1 and A.2 Because of the diversity of sensors available to provide trip signals and the redundancy of the RPS design, an allowable out of service time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months has been shown to be acce> table (Ref. 9) to permit restoration of any inopera)1e channel to OPERABLE status. However, this out of service time is only acceptable provided the associated (continued)

PBAPS UNIT 3 B 3.3-23 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1 BASES ACTIONS A.1 and A.2 (continued)

Function's inoperable channel is in one trip system and the Function still maintains RPS trip capability (refer to Required Actions B.1, B.2, and C.1 Bases). If the ino>erable channel cannot be restored to OPERABLE status witiin the allowable out of service time, the channel or the associated trip system must be placed in the tripped

condition per Required Actions A.1 and A.2. Placing the inoperable channel in trip trip) would conservatively c(or the associated ompensate trip system in for the inoperability, restore capability to accommodate a single failure, and allow operation to continue. Alternatively, if it is not

' desired to place the channel (or trip system) in trip (e.g.,

as in the case where plating the inoperable channel in trip-would result in a full scram), Condition D must be entered

and its Required Action 1aken.

B.1 and B.2 Condition B exists when, for any one or more Functions, at least one required channel is inoperable in each trip system. In this condition, provided at least one channel per trip syste'n is OPERABLE, the RPS still maintains trip capability for that Function, but cannot accomodate a single failure in either trip system.

l Required Actions B.1 and B.2 limit the time the RPS scram logic, for any Function, would not accommodate single failure in both trip systems (e.g., one aut-of-one and one-out-of-one arrangement for a typical four channel Function). The reduced reliability of this logic arrangement was not evaluated in Reference 9 for the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time. Within the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the associated Functicn will have all required channels OPERABLE or in trip (or any combination) in one trip system.

Completing one of these Required Actions restores RPS to a reliability level equivalent to that evaluated in Reference 9, which justified a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowable out of service time as presented in Condition A. The trip system in the more de alternatively, graded state shouldchannels all the inoperable be placed in triptrip in that or, system should be placed in trip (e.g., a trip system with (continued)

PBAPS UNIT 3 B 3.3-24 Revision No.

Amendment !b. 222

RPS Instrumentation B 3.3.1.1 1

BASES ACTIONS B.1 and 8.2 (continued) two inoperable channels could be in a more degraded state than a trip system with four inoperable channels if the two inoperable channels are in the same Function while the four inoperable channels are all in different Functions). The decision of which trip system is in the more degraded state should be based on prudent jud current plant conditions (i.e.gmerit

, Miatand takethe MODE intoplant accountis in .

If this action would result in a stram, it is permissible)to place the other trip system or its inoperable channels in

, trip.

The 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Com)1etion Time is judged acceptable based on the remaining capa)tlity to trip, the diversity of the sensors available to provide the trip signals, the low probability of extensive numbers of inoperabilities affecting all diverse Functions, and the low probability of an event i

requiring the initiation of a scram, Alternately, if it is not desired to place the inoperable channels (or one trip system) in trip where placing the inoperable channel or(e.g., as in the associated tripcase system in trip would result in a scram, Condition D must be entered and its Required Action taken, ful Required Action C.1 is intended to ensure that appropriate actions are taken if multiple, inoperable, untripped channels within the same trip system for the same Function result in an automatic Function, or two or more manual Functions, not maintaining RPS trip capability. A Function is considered to be maintaining RPS trip capability when sufficient channels are OPERABLE or in trip (orthe associated trip system is in trip), such that both trip systems will generate a trip signal from the given Function on a valid signal. For the ty)ical Function with one-out-of-two taken twice logic and tie IRM and APRM Functions, this would require both trip systems to have one channel DPERABLE or in trip (or the associated trip systes;; in trip).

For Function 5 (Main Steam Isolation Valve-Closure), this would require both trip systems to have each channel associated with the MSIVs in three main steam lines (not necessarily the same main steam lines for both trip systems)

(continued)

PBAPS UNIT 3 8 3.3-25 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1 BASES

, I ACTIONS M (continued)

OPERABLE or in trip For Function 8 (Turb'ne forValve-Closure Stop the associated, this trip) wouldsystem in trip).

require both trip ystems to have three channels, each OPERABLE or in tri (or the associated trip system in tri For Functions 12 ( eactor Mode Switch-Shutdown Position)p).

and 13 to have(Manual Scram), this would require both trip systems one channel each OPERABLE or in trip (or the associatedtripsyslemintrip). -l The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is acceptable because it minimizes risk while allowing time for restoration or tripping of-channels.

M Required Action D.1 directs entry into the appropriate Condition referenced in Table 3.3.1.1-1. The applicable condition specified in the Table is Function and MODE or other specified condition dependent and may change as the Required Action of a previous Condition is completed. Each time an inoperable channel has not met any Required Action of Condition A, B, or C and the associated Com>letion Time has expired, Condition D will be entered for tiat channel and provides for transfer to the appropriate subsequent Condition.

E.1. F.1. and G.1 If the channel (s) is not restored to OPERABLE status or placed in trip (or the associated trip system placed-in place in a MODE or other specified condition trip)d in which thewithin t LCD does not apply. The allowed Completion Times are reasonable, based on operating experience,-to reach the specified condition from full power conditions in an orderly manner and without challenging plant systems. In addition,

'the Completion Time of Required Action E.1 is consistent with the' Completion Time provided in LC0 3.2.2, ' MINIMUM CRITICAL POWER RATIO (MCPR)."

(continued)

PBAPS UNIT 3 8 3.3-26 Revision No.

._xrdas t No. 222

c RPS Instrumentation B 3.3.1.1 BASES ACTIONS L1 (continued)

If the channel placedintrip(s)isnotrestoredtoOPERABLEstatusor within the(or the associated allowed tripTime Completion system placed the plant in be must trip)dinaMODEorotherspecifiedcondItioninwhichthe place LC0 does not apply. This is done by immediately initiating action to fully insert all insertable control rods in core cells containing one or more fuel assemblies. Control rods in core cells containing no fuel assemblies do not affect the reactivity of the core and are, therefore not required to be inserted. Actionmustcontinueuntilallinsertable control rods in core cells containing one or more fuel assemblies are fully inserted.

SURVEILLANCE As noted at the-beginning of the SRs, the SRs for each RPS REQUIRENEN13 instrumentation Function are located in the SRs column of Table 3.3.1.1-1.

The Surveillances are n,odified by a Note to indicate that when a channel is placed in an inoperable status solely for i performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , provided the associated Function maintains RPS trip capability. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowance, the channel must be returned to OPERABLE status or the a entered and Required Actions taken. pplicable Condition This Note is based on the reliability analysis (Ref. 9) assumption of the average time required to perform channel Surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months testing allowance '

does not significantly reduce the probability that the RPS will trip w1en necessary.

SR 3.3.1.1.1 s

Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to-a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of (continued)

PBAPS UNIT 3 8 3.3-27 Revision No.

Amendment No. 222

. o .

RPS Instrumentation B 3.3.1.1 BASES i

SURVEILLANCE SR 3.3.1.1.1 (continued)

REQUIREMENTS excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each I CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is l

outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating ex>erience that demonstrates channel failure is rare. T1e CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays ar.sociated with the channels required by the LCO.

SR 3.3.1.1.2 To ensure that the APRMs are accurately indicating the true core average power, the APRMs are calibrated to the reactor power calculated from a heat balance. The Frequency of once

) per 7 days is based on minor changes in LPRM sensitivity which could affect the APRM reading between performances,of SR 3.3.1.1.8.

A restriction to satisfying this SR when < 25% RTP is provided that requires the SR to be met only at a 25% RTP because it is difficult to accuratsly maintain APRM indication of core THERMAL POWER consistent with a heat balance when < 25% RTP. At low power levels, a high degree of accuracy is unnecessary because of the large, inherent margintothermallimits(MCPRandAPLl:GR). At a 25% RTP, the Surveillance is required to have been satisfactorily performed within the last 7 days, in accordance with SR 3.0.2. A Note is provided which allows an increase in THERMAL POWER above 25% if the 7 day Frequency is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching or exceeding 25% RTP. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

(continuedi PBAPS UNIT 3 8 3.3-28 Revision No.

Amendment No. 222

u .

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.3 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the

' intended function. Any setpoint adjustment shall be made consistent with the assumptions of the current plant specific setpoint methodology.

As noted, SR 3.3.1.1.3 is not required to be performed when i

entering MODE 2 from MODE 1, since testing of the MODE 2 l required IRM and APRM Functions cannot be performed in i

i MODE 1 without utilizing jumpers, lifted leads, or movable links. This allows entry into MODE 2 if the 7 day Frequency l

~

is not met per SR 3.0.2. In this event, the SR must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2 from MODE 1.

Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to.

complete the SR.

A Frequency of 7 days provides an acceptable level of_ system average unavailability over the Fre based on reliability analysis (Ref.quency 9). interval and is SR 1.3.1.1.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A Frequency of 7 days provides an acceptable level of system average availability over the Frequency and is based on the reliability analysis of References 9 and 10. (The RPS Channel Test Switch Function's CHANNEL FUNCTIONAL TEST Frequency was credited in the analysis to extend many automatic scram Functions' Frequencies.)

U .3.1.1.5 and SR 3.3.1.1 1

' These Surve111ances are established to ensure that no gaps in neutron flux indication exist from subcritical to power operation for monitoring core reactivity status.

The overlap between SRMs and IRMs is required to be demonstrated to ensure that reactor power will not be increased into a neutron flux region without adequate indication. This is required pr or to withdrawing SRMs from the fully inserted position since indication-is being (continued)

PBAPS UNIT 3 8 3.3-29 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.5 and SR 3.3.1.1.6 (continued)

REQUIREMENTS transitioned from the SRMs to the IRMs.

The overlap between IRMs and APRMs is of concern when reducing power into the IRN range. On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overla) is not maintained. Overlap between IRMs and APRMs exists w1en sufficient IRMs and APRMs l

concurrently have onscale readings such that the transition i between MODE I and MODE 2 can be made without either APRM downscale rod block or IRM upscale rod block. Overlap

' between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are reading on-scale and increasing prior to reaching the SRM's raximum indication. Continued overlap can be achieved b/wit'.1 drawing SRMs to an intermediate position to allow continued rod withdrawls.

As noted, SR 3.3.1.1.6 is only required to be met during entry into MODE 2 from MODE 1. That is, after the overlap requirement has been met and indication has transitioned to the IRMs, maintaining overla) is not required (APRMs may be reading downscale once in MO)E 2).

If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate declared inoperable. Only those appropriate channel channels t (s) hat are required in the current MODE or condition should be declared inoperable.

A Frequency of 7 days is reasonable based on engineering judgeent and the reliability of the IRMs and APRMs.

SR 3.3.1.1.7 The Average Power Range Monitor Flow Biased High Scram Function uses the recirculation loop drive flows to vary the trip setpoint. This SR ensures that the total loop drive flow signals from the flow units used to vary the setpoint is appro)riately compared to a valid core flow signal to verify tie flow signal trip setpoint and, therefore, the APRM Function accurately reflects the required setpoint as a function of flow. If the flow unit signal is not within the ;

appropriate flow limit, the affected APRMs that receive an (continued)

PBAPS UNIT 3 B 3.3-30 Revision No.

Amendment No. 222

e, o ,

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.7 (continued)

REQUIREMENTS input from the inoperable flow unit must be declared inoperable.

judgement, The Frequency operating of 31and experience, days theisreliability based on of thengineerinEs ,

l instrumentation.

SR 3.3.1.1.8 LPRM gain settings are determined from the local flux profiles measured by the Traversing incore Probe (TIP)

System. This establishes the relative local flux profile for appropriate representative input to the APRM System.

The 1000 MWD /T Frequency is based on operating experience with LPRM sensitivity changes.

SR 3.3.1.1.9 and SR 3.3.1.1.14 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assun.ptions of the current plant s)ecific setpoint methodology. For Function 5, 7, and 8 ciannels, verification that the trip settings are less than or equal to the specified Allowable Value during the CHANNEL FUNCTIONAL TEST is not recuired since the channels consist of mechanical switches anc are not subject to drift. An exce) tion to this are two of the Function 7 level switches whic1 are not mechanical. These Scram Discharge Volume (SDV) RPS switches (Fluid Components Inc.) are heat sensitive electronic level detectors which actuate by sensing a difference in temperature. The temperature detectors are permanently affixed within the scram discharge volume piping conservatively below the level (allowable value as measured in gallons) at which an RPS actuation signal will occur. Since there is no drift involved with the physical location of these switches, verifying the trip settings are less than or equal to the specified allowable value during the CHANI.'EL FUNCTIONAL TEST is not required.

Additionally, historical calibration data has indicated that the FCI level switches have not exceeded their Allowable Value when tested.

(continued 1 I PBAPS UNIT 3 B 3.3-31 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1 1

l BASES SURVEILLANCE $R REQUIREMENTS 3.3.1.1.9 and SR 3.3.1.1.14(continued)

In addition function 5 and 7 instruments are not accessible while the un,it is operating at power due to high radiation and the installed indication instrumentation does not

>rovide r

accurate indication of the trip setting. For the l

' unction 9 channels, verification that the trip settings are less than or equal to the specified Allowable Value during the CHANNEL FUNCTIONAL TEST is not required since the instruments are not accessible while the unit is operating at power due to high radiation and the installed indication instrumentation does not provided accurate indication of the trip setting. Waiver of these verifications for the above functions is considered acceptable since the magnitude of drift assumed in the setpoint calculation is based on a 24 month calibration interval. The 92 day Frequency of SR 3.3.1.1.9 is based on the reliability analysis of Reference 9.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components will pass the Surveillance when performed at the 24 month Frequency.

$t 3.3.1.h.h0. SR 3.3.'. 11. !iR 3.3.1.1.12.

$ t 3.3.1. . 35. - and $R - :l.:l.1.1. L6 '

A CHANNEL CAllBRATION is a complete check of the instrument loop and the sensor. This-test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CAllBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the current plant specific setpoint methodology. SR 3.3.1.1.16, however,-is only a calibration of the radiation detectors using a standard radiation source.

As noted for SR 3.3.1.1.11 and SR 3.3.1.1.12, neutron

-detectors are excluded from CHANNEL CALIBRATION because they are passive devices, with minimal drift and because of the i difficulty of simulating a meaningful s,gnal.

i Changes in (continued)

PBAPS UNIT 3 8 3.3-32 Revision No.

Amendment No. 222

, %b 2.

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.' 0. 11. 3.3. .'.LI. 1R 3.3.1.1.12.

REQUIREMENTS SR 3.3.1.1.1n. anc 1R 3. 3. .

.16 (continued) neutron detector sensitivity are compensated for by performing the 7 day calorimetric calibration (SR 3.3.1.1.2) l and the 1000 MWD /T LPRM calibration against the TIPS SR 3.3.1.1.8 . A second note is provided for ;

l Rs 3.3.1.1.1 and 3.3.1.1.12 that allows the APRM and IRM i SRs to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering MODE 2 from '

MODE 1. Testing of the MODE 2 APRM and IRN Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads or movable links. This Note allows entry into MODE 2 from MODE 1, if the_184 day or 18 month Frequency is not met per SR 3.0.2. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR. A t11rd note is proviAc for SR 3.3.1.1.12 that excludes the APRM flow units and associated flow transmitters from this SR since the calibration requirement for these instruments is specified in SR 3.3.1.1.19. As noted for SR 3.3.1.1.10, radiation detectors reasons are excluded from CHANNEL CAllBRATION due to ALARA detectors (when the plant is operating, the radiation are generally in a high radiation arent the steam tunnel). This exclusion is acceptable because the radiation detectors are passive devices, with isinimal drift. The radiation detectors are calibrated in accordance with SR 3.3.1.1.16 on a 24 month Frequency.

The 92 day Frequency of SR 3.3.1.1.10 it conservative with respect to the magnitude of equipment d *ift ' assumed in the setpoint analysis. The Frequencies of SR 3.3.1.1.11 and SR 3.3.1.1.12 are based upon the assumption of a 184 day or an 18 month calibration interval, respectively, in the determination of the magnitude of equipment drift in the setpoint analysis. The Frequencies of SR-3.3.1.1.15 and SR 3.3.1.1.16 are based upon the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the applicable setpoint analysis, feentinuedi PBAPS UNIT 3 8 3.3-33 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1

! SASES SURVEILLANCE SR 3.3.1.1 d1 REQUIREMENTS (continued) This SR ensures that scrams initiated from the Turbine stop l

Valve-Closure and Turbine Control Valve Fast Closure. Trip 011 Pressure-Low Functions will not be inadvertently bypassed when T!!ERMAL POWER is a 30% RTP. This involves i

calibration of the bypass channels. Adequate margins for

! the instrument setpoint methodologies are incorporated into the Allowable Value (s 29.4% RTP which is equivalent to s 138.4 psig as measured from turbine first stage pressure) I and the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively derived from turbine first stage pressure),(THERMAL POWER isthe main byisass valves must remain closed during the calibration at THERMAL POWER a 30% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is no . tonservative-(i.e.,

the Functions are bypassed at a 30% RTP either due to open main turbine bypass valve (s) or other re,asons), then the affected Turbine Sto Valve Fast Closure,Tri p Valve-Closure and Turb4ne Control considered inoperable. pAlternatively, 011 Pressure-Low Functions the bypass channelare canbeplacedintheconservativecondition(nonbypass)he placed in the nonbypass condition, this SR is met and t

. If channel is considered OPERABLE.

The Frequency of 24 months is based on engineering judgment and reliability of the components.

SR 3.3.1.1.17 The LOGIC SYSTEM FUNCTIONAL. TEST demonstrates the 0FERABILITY of the required trip logic rce a specific channel. The functional testing of control rods (LC0 3.1.3), and SDV vent and drain valves overlaps this Surveillance to provide comple(LC0 3.1.8),

te testing of the-assumed safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions'that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with t se reactor at power.

Operating experience has shown that these components will pass the Surveillance when performed-at the 24 month Frequency.

fcontinusdl

'1 .

PBAPS UNIT 3 8 3.3-34 Revision No.

Amendment No. 222

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 1.1.1.1.18 REQUIREMENTS (continued)

This SR ensures that the individual channel response times are maintained less than or equal to the original design value. The RPS RESPONSE TIME acceptance criterton is included in Reference 11.

RPS RESPONSE TIME tests are conducted on a_24 month l Frequency. The 24 month Frequency is consistent with the ,

PBAPSrefuelingcycleandisbaseduponplantoperating '

experience, wh ch shows that random failures of '

instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

SR 1.1.1.1.19 l

The Average Power Range Monitor Flow Biased High Scram function uses the recirculation loop drive flows to vary the trip setpoint. This SR ensures that the flow unit instrumentation that supplies the recirculation flow signal to the APRM system responds to the measured recirculation flow ytthin the necessary range and accuracy by use of a stan i*d pressure source. CHANNEL CAllBRATION leaves the channel adjusted to account for instrument drifts between successive calibrcticns.

The Frequency of 24 months is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power.

Operating experience has shown that these components will

> ass the Surveillance when performed at the 24 month

'requena".

(continued)

P8APS UNIT 3 B.3.3-35 Revision No.

Amendment No. 222

_

ML20217M796

Text

Attachment:

Attachment:

Navigation menu

Search