ML19332A787

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Proposed Tech Specs 3.2.F,4.2.F,6.2-2,6.3-6.5,6.14 & 6.15 Re Water Level Instrumentation & Safety Relief Valve Position Indication.Revision Made in Response to TMI Lessons Learned Task Force Category a Requirements
ML19332A787
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/15/1980
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19332A779 List:
References
RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8009180335
Download: ML19332A787 (7)
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TABLE 3.2.F S U R V E I LL A!!C E IIIS T RUl!ENTA TIO N

?finiaun No.

of Operable Type Instrunent CD Channels Indication C

Instrument and Range Action C

CO Y

00 CD 2 Reactor Water Level Recorder 0-60"

\}) Indicator 0-60" (6) (7) 2 Reactor Pressure Recorder 0-1500 psig (1) (2) (3)

Indicator 0-1200 psig 2 Dryvell Pressure i

Recorder 0-70 psig (1) (2) (3) y 2 Drywell Tc=cerature

" Recorder 0-400*F (1) (2) (3) t Indicator 0-400*F 2 Suppression Chamber Uater Recorder 0-600*F (1) (2) (3)

Teaperature Indicator 0-400*F 2 Suppression Chamber Unter Recorder 0-2 ft. (1) (5)

Level Indicator 0-2 ft.

1 Control Rod Position 28 Volt Indicating )

Lights )

) (1) (2) (3) (4) 1 Neutron !!o n i t o r i n g S R!t , IRM, LPRM )

0-1007. )

kW '

T.

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PBAPU fiOTES FOIt TAnLE 3.2.F

1) From and after the date that'one of these parameters 18 reduced to one indication, continued operation is permissible during the succeeding thirty days unless such inntruuentation in nooner node operable.
2) Fron and efter the date that one of these parameters is noe indicated in the control roon, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.
3) If the requirements of notes (1) and (2) cannot be act, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4) These surveillance instruments are considered to be redundant to each other.
5) In the event that all indications of this parancter are disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the ,

reactor shall be in a Ilo t Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.

6) Uith the number of operable channels less than the ninimum number of instrumentation channels shown in Table 3.2.F, either restore the inoperable channel to an operable status withiu 7 dayn, or he in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
7) If this parameter is not indicated in the control roon, either restore at 1 cast one inoperable channel to operable tatus within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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TABLE ?.2.F UNIT 2 ,

MINIMUM TEST AND CALIERATIO:: FREQUENCY FOR SORVEILLANCE INSTRUMENTATION

.Instrunent-Channel Calibration Frequency Instrument Check

1) Reactor Level Once/ operating cycle Once'Each Shift
2) Reactor Pressure Once/6 nonths Once Each Shift
3) Dryuell Pressure Once/6 months Once Each Shift
4) Drywell Tenperature Once/6 uonths Once Each Shift
5) Suppression Chamber Temperature once/6 nonths once Each Shift 6)' Suppression Chanber Water Level Once/6 nonths once Each Shift
7) Control Rod Position NA Once Each Shift
8) Neutron Monitoring (APRS) Twice Per Ucek once Each Shift I

m

9) Safety / Relief Val'<a Position Once/ Operating cycle O nc e /:lo nt h Indicator (acoustics) i
10) Safety / Relief Valve' Position NA* Once/nonth Indicator (thermocouple)
11) Safety Valve Position once/ operating cycle ,

Once/nonth Indicator (Acoustics)

12) Safety Valve Position NA* Once/aonth Indicator (thercocouple)
  • Perform instrunent functional check once per operating cycle

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TA3LE 4.2.F UNIT 3

!!INI)!U:1 TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMINTATION Instrunent Channel Calibration Frequency Instrument Check 1-) ** Reactor Level .Once/ operating cycle Once Each Shift

  • Reactor Level Once/6 uonths Once Each Shift
2) Reactor Pressure once/6 nonths Once Each Shift ~
3) Drywell Pressure Once/6 nonths Once Each Phift
4) Drywell Tenperature Once/6 months Once Each Shift
5) Suppression Chanber Temperature 'nce/6 months Once Each Shift
6) Suppression Chamber Water. Level Once/6 nonths Once Each Shift
7) Control Rod Position NA Once Each Shift

, 8) Neutron Monitoring ( AP R!!) Twice Per Ueek Once Each Shift

$ 9) Safety / Relief Valve Position Once/ operating cycle Once/ month  !

, Indicator (acoustics) i

10) Safety / Relief Valve Position NA*** Once/ month Indicator (thermocouple) l l

i

11) Safety Valve Position Indicator Once/ operating cycle Once/uonch  !

(acoustics)

12) Safety Valve Position Indicator NA*** Once/nonth (thermoccuple) i i

Deleted when nodifications authorized by Amendment No. 67 are conpleted.

      • Effective when nodifications auchorized by Amendnent No. 67 are conpleted.

Perform instrunent functional check once per operating cycle.

a

g ___ m Superintendent SIM # '

I Asst. Superintendent SLO

  • I Operations Engineer (SIO) l 1 Clerical Engineer Technical (SLO) Engineer Maintenance
  • Security Force ,- Engineer Reactor

% intenance

- Engineer I & C (and/or Results)

= Engineer Health Physica "Cuet7dini

- Engineer Chemistry = Stores 1/S Shift Supt. (SLO)** - Engineers

~

1/S Shift Technical Advisor m * """

" 1/S Shift Supr. (SLO)** ED i

1/S Control Op. Nuclear (IO) * -

At least one of these shall be licensed.

2/S Asst. Cont. Op. Nuclear (LO) **

- Only one of these need to be licensed g during a training and qualification 1/S Plant Op. peri d provided a second SLO is available on site.

1/S Asst. Plant Op.

\ I/S - Number of men per shift. All shift 1/S Aux. Op. positions are marked.

1 IO -

NRC Licensed Operator SLO - NRC Licensed Senior Operator

  1. - Responsible for onsite fire protection activities m- Not applicable with plant ORGANIZATION FOR CONT;UCT OF in cold shutdown condition PLANP OPERATIONS Figure 6.2-2

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L 6.3 Facility Staff Qualifications 6.3.1 Each member of the facility staff shall meet or exceed the ulniauw qualifications of AliSI filU.1-1971 for comparable positions, except for (1) the Enginecr-llealth Physics who shall ueet or exceed the qualificationn of Regulatory Culde 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant j design, and response and analysis of the plant for transients and accidents.

6.4 Training 6.4.1 A reLraining and replaccuent training progran for the facility staff shall be maintained under the direction of the Station Superintendent and shall nect the retinirennnts of Section 5.5 of AtlSI N13.1-1971 and 10 CFR 55, Appendix A.

6.4.2 A training program for the Fire Brigade shall be conducted such that Fire Brigade wenbers couplete an instruction program within a two year period.

Regularly planned meetings will be held every 3 uonths.

6.5 Review and Audit 6.S.1 Plant Operation nevleu Committee (PORC)

Function 6.5.1.1 The Plant Operation Heview Comuittee nhall function to advise the Station Superintendent on all matters related to nuclear safety.

CouponILlon 6.5.1.2 The Plant Operation Review Committee shall be compcsed of the:

Station Superintendent-Chairman Station Assistant Superintendent Engineer - Technical Engineer - !!aint enance "ngineer - Operations Engineer - Results Engineer - Reactor Engineer - Instrument 6 Control  !

Engineer - IIcalth Physics l

Engineer - Chemistry '

Shift Superintendent alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two nlternates shall participate in PORC activitics at any one time.

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PuAPS 6.14 Integrity of Systems Outside Containment The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluida during a nerious transient or accident to an low au practical levein. Thin prograu shall include the following:

1) Provisions establishing preventive maintenance and periodic visual luspection requircuents, and
2) Systou leak test r e q u i r e m e r. t s , to the extent permitted by system design and radiological conditions, for each systeu at a frequency not to exceed refueling cycin i r. t e r va l s . Tho systens subject to this testing are (1) Residual llcat Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) llPCI, and (5) RCIC.

6.15 Iodine !! on i t o ri n g The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

  • under accident conditions. This program shall include the following:
1. Training of personnel, 2, Proceduren for monttoring, and
3. Provisions for maintenance of sanpling and analysis equipment.

Areas requiring nersennel acccss for establishing hot shutdown condition.

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