Text

Responds to 921112 Telcon & Voice Mail Request.Forwards Preliminary Notifications for Plant Recent Shutdown & Excerpts from TS
	ML20126B841
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/17/1992
From:	Perkins K; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Marbet L; AFFILIATION NOT ASSIGNED
References
	NUDOCS 9212220233
	Download: ML20126B841 (23)
	v • d • e

.

4 UNITED STATES p%1. 1 NUCLEAR REGULATORY COMMISSION

{, ,. - i REGION V k / 1450 MARIA LANE WALNUT CREEK, CAUFORNIA 94506-5368 Mr. Lloyd Marbet 19142 S.E. Bakers Ferry Road Boring, Oregon 97009

Dear Mr. Marbet:

This is in response to your call to this office on November 12, 1992, and the request you left on Mr. Phil Johnson's voice-mail. In response to your request, I am enclosing a copy of our preliminary notification for Trojan's recent shutdown and the following excerpts from the Trojan Technical Specifications:

3.4.6.1, 3,4.6.2, and 4.4.6.2, reactor coolant system leakage detection systems, operational leakage limits, and the frequency of leak-rate determinations 3.3.3.1, radiation monitoring instrumentation s

3.3.3.10, radioactive liquid effluent instrumentation if you need additional information regarding Trojan or the ongoing outage for steam generator leak repair, please contact Mr. Greg Cook or Mr. Phil Johnson of this office at (510) 975-0346 or 975-0300, respectively. ;

Your cooperation with us is appreciated.

S ncerely, iN

( UW g ..L.( b '

K. E. Perkins, Jr., Director Division of Reactor Safety and Projects T

9212220233 92t117 ri I PDR ADOCK 05000344

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November 9, 1992 l PRELIMIFARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-V-92-035 This proliuinary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region V staff on this date.

Eacility Licensee Emercency Classification Portland General Electric Co. X Notification of Unusual Event Trojan 1 Alert Prescott, Oregon site Area Emergency Dockets: 50-344 General Emergency Not Applicable

Subject:

UNUSUAL EVENT DECLARED DUE TO STEAM GENERATOR TUDE LEAK At 6:46 a.m. PST (all times are PST) on November 9, 1992, Trojan Nuclear Plant commenced reducing power from 95% when steam generator (SG) tube leakage was detected by the Nitrogen-16 monitors. At 7:00 a.m., with the reactor at 60% power, an Unusual Event was declared when alarms from the offgas monitors indicated that SG tube Icakage was 300 gallons per day (GFD, compared to a Technical Specifications limit of 130 GPD). Power reduction continued and the reactor was tripped from approximately 2%

power at 7:30 a.m. The tube leak was determined to.be in the "B" steam generator, and the hu" steam generator was isolated at 7:46 a.m. At 8:30 a.m. the reactor coolant system was at 530 degrees F and was being cooled r down for RCS depressurization. ;

At 10:10 a.m., with RCS pressure and "B" SG pressure equalized at 940 psig and RCS temperature at-509 degrees F (cooldown still in progress),

the Unusual Event was terminated. Radioactivity released has been a small fraction (less than 1%) of that allowed by the plant's Technical Specifications.

There is local news media interest. The licensee is preparing a press release, and is responding to media inquiries. Region V is also responding to media inquiries. .

The resident inspector is menitoring licensee actions. '

This information is current as of 9:30 a.m.

Contact:

P. Johnson R. Darr (510)97b-0300 (503)S56-3713

l REf,CTCR COOLANT SYSTEtt 3/a.4.5 REACTOR COOLANT SYSTEM LE*tAGE t

LEAKAGE DETECTION SYSTEMS -

LIMITING CONDIT1CN FOR OPERATION 3.4.6.1 The following Rce: tor Cocian: System leak:ge detection systems shall be OPERACLE:

a. The contain :nt atmosphere particulate radioactivity tonitoring system,

b. The containTant surp inventory, and

c. Either the ccr.t3inment air cooler cond?nsate inventory or the containment atmosphere gaseous radioactivity monitoring system.

ArFLICA:ILITY: M30ES 1, 2, 3 and 4.

e ACTION:

(

a. With one of the above required radioactivity monitcring i akaSe e li detection systems inoperable, operations may continue for. up to 30 deys provided: .

l. The other t.tc abcvc required leakage detection systems are OPEPABLE, and

2. Appropriate grab sarples are obtained and analyzed at least -

once per 24 hcurs: .

otherwise, be in COLD SHUTCOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ,

b. With the containment sump inventory ar.d the contair. ment air cocier condensate inventory inoperable, restore the inoperable system to OPERABLE status within 7 days or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE REOUIREMENTS 4.4.6.1 The leakage detecticn systens shall be demonstrated OPERABLE by:

a. Containment atmosphere particulate and gaseous (if being used) i monitoring system-rerformance of CHANNEL CHECK, CHANNEL CALIERA-( [ TION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.0-3 ltem 30.

TRO 'AN-UNIT i 3/4 4-12 Amendment No. 73,99

)

, REACTOR COOLANT SYSTEM SURVt1LLANCE Rt001R[MENTS (Continued) *

b. Containment sump inventory and containment air tooler condens' ate inventory (if being used)-perfortr.ance of CHANNEL CALIBRA110N at l 1 east once per 18 months, e.

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! TROJAN-UNIT 1 3/4 4-13 Amend. No. 12(

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REACTOR COOLANT SYSTEM

( OPERATIONAL LFAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE, c.

400 gallons per day (gpd) total primary-to-secondary leakage through all steam generators and 130 gpd through any one steam generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.

20 GPM total CONTROLLED LEAKAGE from all Reactor Coolant Pumps and 6 GPM CONTROLLED LEAKAGE from any one Reactor Coolant Pump at a Reactor Coolant System pressure of 2230 1 20 psig,

f. Leakage as specified in Table 3.4.6-1 for each Reactor Coolant System Pressure Isolation Valve identified in Table 3.4.6-1.

MPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in COLD SHUTDOWN within 36

, hours. 5 b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate 36 next to within hours, limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in COLD SHUTDOWN within the c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, reactor operation may continue, provided that at least two valves in each high pressure line having a nonfunctional valve are in, and remain in, the mode corresprending to the isolated condition. (Note, however, that this may lead to further ACTION requirements for the individual systems involved.)

! Manual valves shall be locked in the closed position; motor operated valves shall be placed in the closed position and the power supplies deenergized. Whenever integrity of a pressure isolation valve listed in Table 3.4.6-1 cannot be demonstrated, the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition the position of the be other closed recorded daily. valve located in the high pressur,e piping shall applicable.

The provisions of Specification 3.0.4 are not

/

If the provisions above cannot be met, reduce valve leakage to within next 36the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in COLO SHUT 00WN within the

( hours.

TROJAN-UNIT 1 3/4 4-14 Amendment No. 178, 185

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I g 4.4.6.2.1 Reactcr Coolant System leakage: : hall be dc.7.onstrated to be e iwithin each of the above limits by:

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0r1: C# !! 1931 once per iJ "O'J r! .

b. ": * i *:-i r ; t eh cent s in ent t u ," in 'ar te"y a n" =ischae'ge et least cn:c a It

!! :. :::: ; : cr.:

.!/ ;E fr:r. d e. r:::: r .tel 'a

!l pump ses'.; as c. , - e ;; :: 2: " .th:r. t he P.cact:r C001:nt

System press Js s. 2D 20 osig ano the Reactor Coolant Pump l seal return contre 7; lues are tuil open, ,

8: d. Perform:rce Of a Reat:Dr Co:lant 5,istem water inventory balance jf Lt 14;;t ec.06 pi.' 72 h;Jr: 3.rir.; :t:: / :t;;; Op:r: 10n , la is ll e. ficnitocir.; the rea tor head flung: leakoff sy:tcm et Ica:t

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 4.4.5.2.2 Eac, F.es: tor C:olant Syntet. Pre::urr 1s !: tion Valvo treci'ied in Table 3.4.6-1 thall be demonstrated OPERABLE by individually verifying C.) leakage to be within its limit:

a. Prior to entering MODE 2 aft'cr each re' fueling, and"

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUT 00WN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performed in the previous 9 months, and

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

The provisions of Specification 4.0.4 are 'not applicabic for entry into-lt MODES 3 or 4.

I .

l TROJAN , UNIT 1 3/4 4-15 Order dated 4/20/El

TABLE 3.4.6-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES (a)(b)(c) ,

(CHECK VALVES)

VALVE NUMBER FUNCTION 8948 A, B C, D To RCS Cold Legs 8949 A, B, C, D To RCS Hot Legs B818 A, B, C. D RHR to RCS Cold Legs 8819 A, B, C, D S1 to RCS Cold Legs 0905 A B C, D SI to RCS Hot Legs

. 8136 A, B RHR to RCS Hot Legs N01ES:

, (a) Maximum Allowable Leakage (each valve):

1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

2. Leakage rates greater than 1.0 gpm but isss than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the max'imum permissible rate of 5.0 gpm by 50 percent or greater.

3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50 percent or greater.

4. Leakage rates greater than 5.0 gym are considered unacceptable.

5. When leakage tests are performed using a test differential pressure lower than the function maximum differential pressure, observed leakage rates shall be adjusted to function maximum differential pressure values.

(b) To satisfy ALARA requirements, leakage may be measured indirectly (as f rom the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.

(c) Minimum test dif ferentia1' pressure shall tot be less than 150 psid.

TROJAN - UNIT 1 3/4 4-15a Amendment No. 163

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\ IllSTRUMEllTATI0f(

3/4.3.3 M0fitTORit!G liiSTRUMENTAT10!1 RADI AT10ft M0!11TORil!G I!!STRUMEllTAT10tl LIMITil!G C0!!DIT10!I FOR OPERAT10!1 ,

3.3.3.1 The radiation monitoring instrumentation channels shown in Tabic 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTIO!l:

a. Illth a radiation monitoring channel alarm / trip setpoint exceed-ing the value shown in Table 3.3-6, adjust the setpoint to within the 1imit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

(/ ,

b. With one or more radiation monitorirg channels inoperable, take the ACTION shown in Tabic 3.3-6. ..,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not

. applicable.

SURVEILLAl!CE REQUIREMEflTS ,

4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CilAlltlEL CllECK, CHAllNEL CAllDRATION and CilANNEL fullCTIO!!AL TEST operations during the modes and at the frequencies shown in Tabic 4.3-3.

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s TR0JAti-UNIT 1 '3/4 3-33 ;

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TABLE 3.3 6 (Continued)

TABLE NOTATION ACTION 19 - With the number of channels OPERABLE less than required -

by the '4inimum Channels OPtRABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 20 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate an alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel (s) to OPERABLE' status within 7 days of the event, or

2) prepare and submit a special report to the Commission pursuant to Specification 6.9.2 withir. the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

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ff ,, TROJAN-UNIT 1 3/4 3-35 Amendment No. 99.105 1

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lHSTRUMENTATION RADI0 ACTIVE LIOU10 EFFLUENT It'STRUMENTATION I LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.'. are not exceeded.

,APPLICAEILITY: As shcwn in Table 3.3-12.

ACTION:

a. With a radioactive liquid effluent monitoring instrumen-tation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, immediately suspend the release of radioactive liquid -

ef fluents monitored by the affected channel or de:lare..the channel inoperable,

b. With less than the minimum number of r'adioactive liquid effluent monitoring instrumentation channels operable, take the ACTION C shown in Table 3.3-12. With the incperable instrumentation channels not returned to cperable status within 30 days, iden-l tify the cause of the inoperable channels in the Semiannual Radiological Environmental Report in lieu of any other report,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.10.1 The setpoints shall be determined in accordance with pro-cedures as described in the ODCM and shall be recorded.

4.3.3.10.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST cperations at the frequencies shown in Table 4.3-8.

i TROJAN-UNIT 1 3/4 3-54 Amendment No. 99 e

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-4 -TABLE 3.3-12 - -

g h RADIDACTIVE L1001D EFFLUENT MONITORING INSTRUMENTATION 4:

,5 MINIMUM

'd CHANNELS

. INSTRUMENT .

pPERABLE APPliCA9TLITY - ACTION

1. Gross Radioactivity Monitors Providing Automatic Tertslnation of Release

23

a. Liquid Radwaste Effluent Line 1 (PRM-9)

24

b. Steam Generator Blowdown 1 Effluent Line (PRM-10) or

w Steam Generator Blowdown Ion 2 Exchanger Ef fluent (PRM-17)

$ 2. Gross Radioactivity Monitors

Not Providing Automatic '

l Terraination of Release j

a. Congonent Cooling Water System 1 At all times 25 Train A (PRM-7) ,

b. Component Cooling Water System 1 At all times 25 Train B (PRM-8) m a

During releases via this pathway.

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i TABLE 3.3-12 f Continued)

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.g RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION E-

~ MINIMUM i -e CHANNELS

. INSTRUMENT OPERABLE

~

APPLICABILITY -

ACTION

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1

26 (FT-4044 or FIY-4098) i- b. . Discharge Structure 1

26 i

(FR-3495)

(-

c. ' Steam Generator 810wdown 1

26 l Effluent Line

t* (FI-6715 or FI-4921) l l

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{' Onl E

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+

1. 8

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During releases via this pathway..

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TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 23 With the number of channels OPERABLE less than r'equired by the*

Hinimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Table 4.11-1, and;

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving, and;

3. Initiate corrective action to return the channels to OPERABLE status; or Otherwise suspend release of radioactive effluents via this pathway.

ACTION 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are

( analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/ gram;

1. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when release is discharged into the Columbia River.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, collect and analyze l '

grab samples for gross radioactivity (beta or gamma) at a lower

limit of detection of at least 10 7 pCi/ml as defined in Table 4.11-1; -

1. At least once per 7 days when CCWS radioactivity is less than 10 5 pCi/ml and no indication of leakage from the '

radioactive systems to the CCWS is observed.

2. Otherwise, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

~

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated e at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

1 TROJAN-UNIT 1 3/4 3-57 Amendment No. 55, 187; l' f:-

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l C N O g TABLE 4.3-8 RADIDACTIVE L10UID EFFLUENT MONITORING INSTRUMENTATION SURVElttANCE REQUIREMENTS

^

t CHANNEL

! U CHANNEL SOURCE CHANNEL FUNCTIONAL a INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta or Ganrna Radioactivity Monitors Providing Alarm and Automatic Isolation i

a. Liquid Radwaste Effluents Line D* P R(1) Q(1) f (PRM-9)

b. Steam Generator Blowdown Effluent D* M R(1) Q(1)

Line (PRM-10) w c. ' team Generator Blowdown Ion D* M R(1) Q(1)

Exchanger Ef fluent (PRM-17) w h 2. Gross Beta or Gama Radioactivity Monitors Providing Alarm But Nut Providing Automatic Isolation Component Cooling' System (PRM-7. -8) D M R(1) Q(1) !

3. Flow Rate Monitors i

a. Liquid Radwaste Effluent Line D* N/A R** N/A I

( FT-4044/FIY-4098) l

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b. Discharge Structure (FR-3495) D* N/A R** N/A

('w g c. Steam Generator Blowdown Line D* N/A R** N/A g ,

(FI-6715 or FI-4921) y c.

O

During releases via this pathway.

3 ** Applies only to flow indication loop.

(1) The Channel Functional Test shall, where applicable, include verification that automatic g isolation of the ef fected pathway and/or control room annunciator occurs if:

1) Instrument indicates above alarm trip setpoint.

2) Instrument indicates a downscate failure.

3) Controls not in OPERATE mode, or instrument de-energized. l m -

f INSTRUMENTATION

_ RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORI LIMITINr CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous process and ef fluent monitoring instrumen-tation channels shown in Table 3.3-13 shall be OPERABLE with their trip setpoints set to ensure that the limits of Specification 3.11.2.1 are ,

3.4.6.1 and 3.9.9. as applicable.not exceeded and to comply with the ( r APPLICAB1t1TY: As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous process or ef fluent monitoring instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-13, adjust the setpoint to within operable.

the limit without delay or declare the channel in-b.

With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. With the inoperable instrumentation channels identified in Table 3.3-13

. items 1, 2, 3c, 4 and 5 not returned to OPERABLE status within 30 days, identify the cause of the inoperable channels in the Semiannual other report.Radiological Environmental Report in lieu of any c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.1 11.1 The setpoints shall be determined in accordance with procedures _

as de=cribed in the 00CH and shall be recorded.

4.3.3.11.2 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL _

FUNCTIONAL TEST operation at the frequencies shown in Table 4.3-9.

, - - , . . m -_e.- - - , - .- - - - - - - . . , ~ , - . , - - - , , ,-m.-r, -- , . --- . ,w e e .-

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

TABLE 3.3-13 . - ;

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.g -RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATI -

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MINIMUM ALARM 3

% INSTRUMEA"i CHANNELS APPLICABLE TRIP OPERABLE _ MODES SETPOINT ACTION

1. Waste Gase Holdup System Noble Gas Activity Monitor - 1

Providing Alarm and Automatic ***

31 Termination of Release (PRM-4A)

2. Waste Gcs Holdup System Explosive 3

Gas' Monitoring System

, . Oxygen'Monttor(a)

1. 2(a) **

N/A 29 3a. Containment ~ Ventilation' Isolation

a. Particulate Activity Monitor 1 1, 2, 3.'4,

.(PRM-1A) S 2 Times 33 and 6 Background i

b. Iodine Activity Monitor (PRM-18)

] 1 1, 2, 2, 4, S 2 Times 33 and 6 Background

c. Low-level Noble Gas Monitor

.k. (PRM-IC) 1 1,2,3,4, S 2 Times . 33 n and 6 Background ,,

[ d. High Level Noble Gas Monitor 1**** 1,2,3.4, 3 (PRM-1D) i2 Times 33 and 6 Background O

to

,- (a). remote For purposes indicator of onoxygen monitor requirements, two' channels shall be operable from sensing elem'ent to '

panel C-151.'

0- A single alarie shall be operable in the control room In order to

, satisfy the requirement of Specification 4.?).2.6.1 for continuous monitoring.

p n _ m^- _

TABLE 3,3-13 (Continued) .

h M RADIDACTIVE GASEOUS PROCESS AND EFFLUENT HONITORING INSTRUMENTATION

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E ~

MINIMUM O #

CHANNELS ALARM

, INSTRUMENT / ' PLICABLE TRIP DPERABLE A0 DES SETPOIH1 ACTION 3b. RCS teakage Detection

a. Particulate Activity [ Monitor (PRM-1A) 1 1,2,3 N/A 32 and 4

b. Low level Noble Gas Monitor !

1 1, 2, 3, (PRM-lC) N/A 32

, and 4

c. High level Noble Gas Monitor 8 1**** 1,2,3 1: N/A 1

s (PRM-lD) 32 and 4 Y 3c. Containment Purge Effluent Monitoring S

a. Low level Noble Gas Monitor 1 *

(PRM-1C) W/A 28

b. High level Noble Gas Moniter 1**** -

(PRM-1D) N/A 28 y c. Iodine Composite Sampler 1

E N/A -30

~ & d. Particulate Composite Sampler

1 N/A 30 1

e. Effluent System Flow Rate *

'W . Heasuring Device (FR-5600) 1 N/A 27 E f. Sampler Flow Rate Measuring 1

Device for Compos 1te Sampler N/A 27 O

(. p d.. . t 1 ..

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. t Y TABLE 3.3-13 (Continued) ;

i

. .o i N RADIDACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION T t

.E _

U -

MINIMI!M ALARM t CHANNEPS !

l INSTRUMENT APPLICABLE TRIP

OPERABLE MODES SETPOINT ACTION !

4. Auxiliary Bu11 ding Ventilation Monitoring System a.' Noble Gas Activity Monitor (PRM-2C) i 1

t 28

b. Iodine Composite Sampler 1

N/A 30

c. Particulate Composite Sampler 1

N/A 30 ;

i

$_ .d. Sampler Flow Rate Measuring Device !

1 *

, for composite Sampler N/A 27 S.

Condenser Air: Ejector Monitoring System !

a. : Noble Gas' Activity Monitor 1

i (PRM-6A 'or 69) N/A 28 ;

b. Iodine Composite Sampler, !

! E 1

N/A , 30 i j

k c. Particulate Composite Sampler 1

i

_ P. N/A 30 k

g d. Effluent System Flow Rate .

1

N/A i

, Measuring Device (FR-3100) 27 1 I

.o , i

, , s. .-Sampler Flow Rate Measuring 1 i *- T'

N/A h

. . Device 27 l

-- r

.y .

[ "

O i

I .

- TABLE 3.3-13 (Continued) 8 g PADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORIfiG INSTRUMENTATIOTI E MINIMUM ALARM Z CHANNELS APPLICABLE TRIP m INSTRUMENT OPERABLE _ MODES SETPOINT ACTION

6. Post-Accident Monitoring Systems

a. Containment floble Gas Effluent 1,2,3,4 ** ** 34 Monitor (PRM-1E) 1

b. Containment Effluent Iodine Sampler (High Range) 1 1, 2, 3, 4 N/A 34 5 c. Auxiliary Building Noble Gas w Ef fluent Monitor (PRM-20) 1 1, 2, 3, 4 34 E,

7 d. Auxiliary Building Effluent Iodine Sampler (High Range) 1 1,2,3,4 N/A 34

e. Condenser Air Ejector Noble Gas 1,2,3,41 *****

Effluent Monitor (PRM-6C) 1 34 y f. Condenser Air Ejector Effluent g Iodine Saepler (High Range) 1 1,2,3,47 N/A 34

( k g. Main Steam Line Noble Gas Activity l A Monitors (PRM-16A, -16B, -16C, -160) 1/ steam 1, 2, 3, 4 N/A 34 2, ifne Es w

n' e

9 i _._

TABLE 3.3-13 (Continued)

TABLE NOTATION

During tvieases via this pathway

- During waste gas compressor opera. tion. -,.

- - Set to assure that the limits of 3.11.2.1 are met.

- - - Hinimum is on scale channels operable requirement does not apply if-PRM-1C and operable.

- - - - Setpoint calculated in accordance with 4.3.3.11.1. '

Only applicable in Modes 3 and 4 if the condenser has a vacuum. , t ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 28 g With the number of channels OPERABLE less than required by the

' Minimum Channels OPERABLE requirement, effluent releases via this

' pathway may continue provided grab samples are taken at leas + once

! per 2424 within hours and these samples are analyzed for gross activity hours.

! If the primary-to-secondary leakage increases j more than 10 gpd during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the sampling

f requency to once per for condenser air ejector discharge shall be increased 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION 29 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas compressors may continue provided grab samples are taken and analyzed once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

. With both channels inoperable, opera-tion of the vaste gas compressors may continue provided grab samples are taken and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 30 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken and analyzed once stable, per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when Plant release rates are anticipated to be if transient release rates are anticipated, a sufficient number of additional samples will be taken to document release rates.

ACTION 31 With the number of channels OPER'ABLE less than required by the Mini-mum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a.

At least two analyzed, andindependent samples of the tank's contents are b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup, and

! c.

! Initiate corrective action to return the inoperable channels to OPERABLE status; or Suspend release of radioactive effluents via this pathway.

1ROJAN-UNIT l 3/4 3-63 Amendment No. 97, 105, 108

c g 4..

IMLE 4.3-9 RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-4 .

8 CHANNEL MODES IN WHICH

);" CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE y INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED C ,

5 1. Waste Gas Holdup System Noble Gas

~'

Activity Monitor - Providing P P(a) g g(4) gfA Alarm and Automatic Termination of Release (PRM-4A)

2. Waste Gas Holdup System' Explosive Gas Monitoring System

a. Oxygen Monitor D** N/A I II I N/A N/A Q

3a. Containment Ventilation Isolation S N/A R M(2)(4) 1,2,3,4, (PRM-1A, 18, 1C. 1D) -

and 6 3b. RCS Leakage Detection t 5 N/A R M(2)(4) 1,2,3,4, u (PRM-1A, 1C, 10) and 6 3c. Containment Purge Effluent

'I' Monitoring

a. Low level Noble Gas Monitor D* M R MI2)(4) N/A (PRM-1C)

b. High level Noble Gas Monitor D* M(a) ' R M(2)(4) N/A (PRM-10)

c. Iodine Composite Sampler W(3) N/A N/A N/A N/A

,$' d. Particulate Composite Sampler W(3) N/A N/A N/A N/A E e. System Effluent Flow Rate D* N/A R N/A N/A y Measuring Device (FR-5600)

f. Sampier Flow Rate Measuring W* N/A N/A N/A N/A I

,5 Device for Composite Sampler E

~

(a) Source checks for PRM-4A and PRM-10 are accomplished by verifying that their channels are indicating above zero. These channels have no check sources, but are monitored above a zero reading by an

~

3 installed keep-alive source.

(b) The staggered channel calibration of the oxygen monitors shall include those items of a functional check nature, r9

ML20126B841

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