Text

Proposed Tech Spec Change Request 90,revising Reporting Requirements in Accordance W/Generic Ltr 83-43 to Comply w/10CFR50.72 & 50.73
	ML20084K273
Person / Time
Site:	Beaver Valley
Issue date:	05/02/1984
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20084K263	List: ML20084K260; ML20084K265; ML20084K273;
References
	GL-83-43, NUDOCS 8405110161
	Download: ML20084K273 (39)
	v • d • e

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T' DEFINITIONS REPORTABLE EVENT

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1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

CONTAILMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

1.3.1 All penetrations required to be closed during accident conditions are either:

a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or

b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.

1.8.2 All equipment hatches are closed and sr.aled.

1.8.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3.,

and 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2.

CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accu-racy to known values of the parameter which.the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include-the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall incluce, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

BEAVER VALLEY - UNIT 1 1-2 PROPOSED WORDING 8405110161 840502 PDR ADOCK 05000334 P pm

REACTIVITY CCMPOL SYSTDG -

POSITION INDICATICE SYSTDE-OPERATING LIMITING CCEDITION FOR OPERATION 3.1.3.2 'Ihe shutdown and control rod position indication system shall be OPERABLE as follows:

Group Demand Counter (1),1 per group Individual analog rod position instrument charmel,1 per rod + 12 steps (1) accuracy (3)

Autcznatic Pod Position Deviation Monitor (2), setpoints 12 steps, or, setpoint verification by recording analog / digital rod position at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The provisions of Specification 3.0.4 are not applicable to this monitor.(3),

(1) During the first hour followmg rod motion, the group demand counter is the primary indicator of precise rod position infor-mation, with the analog enannels displaying general rod movment information. For power levels below 50%, a 1-hour thermal soak time is allowed before the analog channels are recuired to per-form within the specified accuracy.

(2) For power levels below 50% a one hour thermal soak time is allowed. '1herefore, if a Bod Position Deviation Monitor alarm clears itself within this hour, the alarm is considered invalid.

(3) Malfunctions of the group dercand counters, analog RPI or Rod Deviation Itnitor, providing no actual rod misalignment existed during the malfunction, shall be reported in the monthly cperating report.

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! BEAVER VALLEY UNIT 1 3/4 1-20 Proposed Itrding

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9 INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 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 Specifica- t tion 3.11.1.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (0DCM).

APPLICABILITY: During releases through the flow path.

t ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected !

channel or correct the alarm / trip setpoint.

b ., With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Semi-Annual Effluent Release Report l why the inoperability was not corrected in a timely manner.

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

l SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

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BEAVER VALLEY - UNIT 1 3/4 3-53 PROPOSED WORDING

s 9 INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION I

LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation i channels shown in Table 3.3-13 shall be OPERABLE with their alarm /

trip setpoints set to ensure that the limits of 3.11. 2.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (00CM).

APPLICABILITY: During releases through the flow path.

ACTION: ,

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative i than a value which will ensure that the limits of 3.11.2.1 are met, immediately. suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm / trip setpoint.

b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.J-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Semi-Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

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

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$ RVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL i CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

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BEAVER VALLEY - UNIT 1 3/4 3-59 PROPOSED WORDING

REACIOR COOIAVf SYSTEM SAFELY VALVES - SHUTDOWN LIMITING CONDITION EUR OPERATIN 3.4.2 A mininun of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 PSIG 1%.

APPLICABILITY: 20 DES 4 and 5 .

ACTICN:

a. With no pressurizer code safety valve OPERABLE, (Mintely suspend all cperations involving positive reactivity cPanges and place an OPERABLE FHR loop into operation in the shutdown cooling mode,

b. Failure of.a pressurizer code safety valve to operate wten required >

shall be reported' to the Ccmnission within 30 days pursuant to Specification 6.9.2.

r SURVRTT.TAtEE leUJMCIMS 4.4.2 The pressurizer code safety valve shall be demonstrated OPERABLE per Surveillance Requirement 4.4.3.

BEAVER VA N - UNIT 1 3/4 4-5 PROPOSED hDRDING

REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING -

LIMITING CONDITION FdR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG 1%. '

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . .

b. Failure of a pressurizer code safety valve to operate when required shall be reported to the Commission within 30 days pursuant to Specification 6.9. 2.

SURVEILLANCE REQUIREMENTS i

4.4.3 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2485 PSIG 1%, in accordance with Section XI of i the ASME Boiler and Pressure Vessel Code,1974 Edition.

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I BEAVER VALLEY - UNIT 1 3/4 4-6 PROPOSED WORDING

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E REACTOR COOLANT SY'STEM SURVEILLANCE REQUIREMENTS (Continued)

c. Results of steam generator tube inspections which fall into .

Category C-3 shall be reported to the Commission pursuant to l Specification 6.6 prior to resumption of plant operation.

The written report shall provide a description of investigations conducted to determine cause of the tube degradation and cor-rective measures taken to prevent recurrence.

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BEAVER VALLEY - UNIT 1 3/4 4-10b PROPOSED WORDING i

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c REACTOR COOLANT SYSTEf1 BASES The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice -inspection of steam gen-erator tubes is based on a modification of Regulatory Guide 1.83, Revi-sion 1. Inservice inspection of steam generator tubing is essential in l order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degrada-tion due to design, manufacturing errors, or inservice conditions that lead to corrosion. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube deg-radation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those parameter limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these parameter limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limita-tion of steam generator tube leakage between the primary coolant system -'

and the secondary coolant system (primary-to-secondary leakage = 500 gallons per day per steam generator). Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plant have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspec-tion, during which the leaking tubes will be located and plugged.

Wastage-type defects are unlikely with the all volatile treatment (AVT) of secondary coolant. However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam gen-erator tube examinations. Plugging will be required of all tubes with imper-fections exceeding the plugging limit which, by the definition of Specifi-cation 4.4.5.4.a is 40% of the tube nominal wall thickness. Steam generator i tube inspections of operating plant; have demonstrated the capability to ,

reliably detect degradation the . hes penetrated 20% of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.6 prior to resumption of plant operation. Such

. cases will be considered by the Commission on a case-by-case basis and may result ~ in a requirement for analysis, laboratory examinations, test, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

BEAVER VALLEY - UNIT 1 8 3/4 4-2a PROPOSED WORDING

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REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. 51.0 #C1/ gram DOSE EQUIVALENT I-131, and

b. s100/T # Ci/ gram.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1, 2 and 3*

a. With the specific activity of the primary coolant >l.0,uCi/ gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue For up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time. The provisions cf Specification 3.0.4 are not applicable.

b. With the specific activity of the primary coolant >l.0mC1/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one contin-uous time interval or exceeding the limit line shown on Figure 3.4-1, be in H0T STANDBY with T avg <500 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With the specific activity of the primary coolant > 100/E Ci/ gram, be in HOT STANDBY with T,yg <500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

?!0 DES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant >l.0 Ci/ gram DOSE EQUIVALENT I-131 or>100/T Ci/ gram, perform the sampling and analysis requirements of it'em 4a of Table 4.4-12 until the specific activity of the primary coolant is restored to within its limits. Immediately notify the Commission pursuant to 10CFR50.72 (declaration of any of the Emergency Classes specified in the Emergency Preparedness Plan). Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9. 2.

containing the results of the specific activity analyses together with the following information:

With T avg a 500"F 3EAVER VALLEY - UNIT 1 3/4 4-18 PROPOSED WORDING

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

a. At the first refueling outage, dye penetrant inspections shall be performed on all six reactor vessel nozzles and volumetric inspections shall be performed on at least two nozzles in the same manner as that conducted in the baseline inspection.

b. At the second refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultra- '

sonic examination shall be performed on all six nozzle to safe end welds from the outside diameter.

At t."e third refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultra-sonic examination shall be performed on all six nozzle to safe end welds from the outside diameter. Ultrasonic examination shall be performed on the three outlet nozzle to safe end welds from the inside diameter.

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BEAVER VALLEY - UNIT 1 3/4 4-29 _

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REACTOR COOLANT SYSTEM 3/4 4.11 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.11 (Two) power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3. .

' ACTION:

a. With less than 2 PORV(s) operable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore two PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the 4 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With one or more block valve (s) inopreable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT-DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

c. Failure of a power operated relief valve to operate when required shall be reported to the Commission within 30 days pursuant to Specification 6.9.2.

SURVEILLANCE REOUIREMENTS 4.4.11.1 Each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL CHECK of the position indication, excluding valve operation and

b. By performance of a CHANNEL CALIBRATION in accordance with Table 4.3 -7on the operable PORV(s) Control Channel (s) .

4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

4.4.11.3 The emergency power supply for the PORVs and block valves shall ;

be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel.

BEAVER VALLEY - UNIT 1 3/4 4-31 PROPOSED WORDING l

c' CONTAINMENT SYSTB4S CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.ti.l.6.1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Liner Plate and Concrete The structural integrity of the containment liner plate and concrete shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by:

a. a visual inspection of the accessible surfaces and verifying no apparent changes in appearance or other abnormal degradation.

b. a visual inspection of accessible containment liner test channels prior to each Type A containment leakage rate test. Any contain-ment liner test channel which is found to be damaged to the extent

! that channel integrity is impaired or which is discovered with a l

vent plug removed, shall be removed and a protective coating shall l be applied to the liner in that area.

c. a visual inspection of the dome area prior to each Type A contain-l ment leakage rate test to insure the integrity of the protective l

coating. If a loss of integrity of the protective coating is observed, any vent plug to a test channel which may be in the area where the protective coating has failed shall be seal welded and then the protective coating shall be repaired.

4.6.1.6.2 Reports An initial report of any abnormal degradation of the containment structure detected during the above required tests and inspec-tions shall be made within 10 days after completion of the surveillance l requirements of this specification, and the detailed report shall be submitted pursuant to Specification 6.9.2 within 90 days after completion. This l report shall include a description of the condition of the liner plate and concrete, the inspection procedure, the tolerances on cracking and the cor-rective actions taken.

BEAVER VALLEY - UNIT l 3/4 6-10 PROPOSED WORDING

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PLANT SYSTEMS 3/4.7.14 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.14.1 The fire suppression water system shall be OPERABLE with;

a. Two high pressure pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header,

b. An OPERABLE flow path capable of taking suction from the Ohio River and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves anf the first valve ahead of the water flow alann device on each sprink'er, hose standpipe or spray system riser required to be OPERABLE per Specifications

3. 7.14. 2 and 3. 7.14.4.

APPLICABILITY: At all times.

ACTION:

a. With one pump inoperable, restore the inoperable equipment to OPERABLE status within 7 days, or, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within l the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The pro-visions of Specifications 3.0.3 and 3.0.4 are not applicable.

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and l 2. Submit a Special Report in accordance with Specification l 6.9. 2; i

l a) By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l b) Confirmed by telegraph, mailgram or facsimile trans-mission no later than the first working day following I the event, and

! BEAVER VALLEY - UNIT 1 3/4 7-35 PROPOSED WORDING l

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PLANT SYSTEMS LOW PRESSURE C0 SYSTEM 7

LIMITING CONDITION FOR OPERATION 3.7.14.3 The 10 ton low pressure C0 system serving the following areas shall be OPERABLE with a minimum lev 81 of 30% and a minimum pressure of 275 psig in the associated storage tank.

a. Cable Tray Mezzanina

b. Cable Vaults

c. Diesel Generator Room APPLICABILITY: Whenever equipment in the low pressure CO2 protected areas is required to be OPERABLE.

ACTION:

.a. With the above required low pressure C07 system inoperable, es-tablish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the system to OPERABLE status within 14 days or, prepare and l submit a Special Report to the Commission pursuant to Specifi-cation 6.9.2 within 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,

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.14.3 The above required low pressure CO system shall be demonstrated 2

OPERABLE:

a. At least once per 7 days by verifying CO2 storage tank level and pressure, and

b. At least once per 18 months by verifying:

1. The system valves and associated ventilation dampers actuate manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test".

BEAVER VALLEY - UNIT 1 3/4 7-41 PROPOSED WORDING

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at anytime from the site (See Figure 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, .

Column 2 for radionuclides other than dissolved or entrained noble '

gases. For dissolved or en shall be limited to 2 x 10~ grained

, C1/mlnobletotalgases, the concentration activity. ,

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore concentration udthin the above limits, and

b. Immediately notify the Commission pursuant to 10CFR50.72 (decla-ration of any of the Energency Classes specified in the EPP), and

c. Submit a Special Report to the Commission within 30 days in accor-dance with Specification 6.9.2.

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

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-l*.

4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of the ODCM to assure that the concentration at the point of release are maintained within the limits of specifica-tion 3.11.1.1.

Radioactive liquid discharges are normally via batch modes.

Turbine Building Drains shall be monitored as specified in Section 4.11.1.1.3.

BEAVER VALLEY - UNIT 3/4 11-1 PROPOSED WORDING

4' RADI0 ACTIVE EFFLUENTS DOSE j LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to MEMBER (S) 0F THE PUBLIC FROM radioactive materials in liquid effluents released from the site (see i Figure 5.1-2) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, !

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b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. i t APPLICABILITY: At all times. !

i ACTION: :

a. With the calculated dose from the release of radioactive materials !

in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to l <

Specification 6.9.2, a Special Report which identifies the -

cause(s) for exceeding the Ifmit(s) and defines the corrective 4 actions to be taken to reduce the releases, and the proposed ,

corrective actions to be taken to assure the subsequent releases ;

will be within the above limits. (This Special Report shall also '

, include (1) the results of radiological analyses of the drinking 2'

water scurce and (2) the radiological impact on finished drinking i water supplies with regard to the requirements of 40 CFR 141, l Safe Drinking Water Act).* r

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l

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Applicable only if drinking water supply is taken from the receiving water body.

i-BEAVER VALLEY - UNIT 1 3/4 11-6

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c' RADI0 ACTIVE EFFLUENTS S

LIQUID WASTE TREATMENT LIMITING CONDITION OF OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge i

when the projected doses due to liquid effluent releases from the site (See Figure 5.1-2) when averaged over 31 days would exceed 0.06 mrem to the total body or 0. 2 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With liquid waste being discharged without treatment and exceeding the limits specified, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes l the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) takerf to restore the , inoperable equipment to opera-tional status, and

3. Summary description of action (s) taken to prevent a recurrence,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l 1

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BEAVER VALLEY - UNIT 1 3/4 11-8 PROPOSED WORDING

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RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to :s 10 curies, excluding tritium and dissolved or entrained noble gases,

a. BR-TK-6A (Primary Water Storage Tank)

b. BR-TK-6B (Primary Water Storage Tank)

c. LW-TK-7A (Steam Generator Drain Tank)

d. LW-TK-78'(SteamGeneratorDrainTank)

e. Miscellaneous temporary outside radioactive liquid storage tanks.

APPLICABILITY: At all times.

. ACTION:

a. With the quantity of radioactive material in any of the above ,

listed tanks exceeding the above limit, immediately suspend ,

all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and

b. Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description l of activities planned and/or taken to reduce the contents to within the specified limits.

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

l SURVEILLANCE REQUIREMENTS !

4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents

at least once per 7 days when radioactive materials are being added to the tank.

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BEAVER VALLEY - UNIT 1 3/4 11-10 l PROPOSED WORDING

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. RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITIFG CONDITION FOR OPERATION 3.11.2.1 The dose rate in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents fraa the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be sE 500 mrem /yr to the total body and 5;3000 mrem /yr to the skin, and

b. The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than 8 days shall be:E1500 mrem /yr to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s), and r

b. Submit a Special Report to the Canmission within 30 days pursuant to Specification 6.9.2.

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

i l SURVEILLANCE REQUIREMENTS l

! 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.

1 i

BEAVER VALLEY - UNIT 1 3/4 11-11 l PROPOSED WORDING

b RADI0 ACTIVE EFFLUENTS DOSE, N0BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2. 2 The air dose in unrestricted areas (See Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to 65 mrad for gamma radiation and

$10 mrad for beta radiation.

b. During any calendar year, to 110 mrad for gamma radiation and 620 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare l and submit to the Commission within 30 days, pursuant to <

Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not l applicable.

SURVEILLANCE REQUIREMENTS 4.11. 2. 2 Dose Calculations. Cumulative dose contributions shall be determined in accordance with the ODC!! at least once every 31 days.

BEAVER VALLEY - UNIT 1 3/4 11-15 PROPOSED WORDING k

e v - - -

RADI0 ACTIVE EFFLUENTS m .

DOSE, RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE F0ml, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11. 2.3 The dose to MEMBER (S) 0F THE PUBLIC from radiciodines and radio-active materials in particulate form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter to $7.5 mrem to any organ, and

b. During any calendar year to $15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to l Specification 6.9.2, a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases 9d11 be within the above limits.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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b.

l SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

BEAVER VALLEY.- UNIT 1 3/4 11-16 PROPOSED WORDING

a' RADI0 ACTIVE EFFLUENTS GJ!'00S RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11. 2.4 The Gaseous Radweste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0. 2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within (

30 days, pursuant to Specification 6.9. 2, a Special Report which I includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to operational status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11. 2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCit.

BEAVER VALLEY - UNIT 1 3/4 11-18 PR', POSED WORDING e

S RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11. 2.5 The quantity of radioactivity contained in each gas storage tank shall be limited to s52000 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and

b. Submit a Special Report to the Commission within 30 days pursuant to Specifi. cation 6.9. 2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

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

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i l

SURVEILLANCE RE0VIREMENTS ,

4.11.2.5.1 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least i

l once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank when the Waste Gas Decay Tank Monitor (RM-GW-101) is not operable.

l 4.11.2.5. 2 The Waste Gas Decay Tank Monitor (RM-GW-101) operability shall be determined in accordance with Table 4.3-13 unless sampling pursuant to 4.11.2.5.1 is being conducted, i

BEAVER VALLEY - UNIT 1 3/4 11-20 PROPOSED WORDING i

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION ,

3.11. 2.6 The concentration of oxygen in the waste gas holdup system shall be limited to $2% by volume whenever the hydrogen concentration exceeds 4% by volume.

,,PPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the weste gas holdup system

>2% by volume, immediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to 44% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 2% by volume within twelve hours,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11. 2.6 The concentrations of oxygen in the waste gas holdup l system shall be determined to be within the above limits by contin-l uously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification

3.3.3.10 or monitoring in conjunction with its associated action state- -

l ment.

l l

l c BEAVER VALLEY - UNIT 1 3/4 11-21 PROPOSED WORDING

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be used, as applicable, to solidify and package radioactive wastes, and to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71. Methods utilized to meet these requirements shall be described in facility proceduces and in the Process Control Program (PCP).

APPLICABILITY: At all times.

ACTION:

a. With the applicable requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend affected shipments of solid radioactive wastes from the site.

b. The provisions of Specifications 3.0.3 and 3.0.4 are l not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1.1 Prior to shipment, solidification shall be verified in accordance with Station Operating Procedures.

4.11.3.1. 2 Repo rts. The semi-annual Radioactive Effluent Release Report in Spec 1fication 6.9.1.12 shall include the following information for each type of solid waste shipped offsite during the report period:

a. container volume;

b. total curie quantity (detennined by measurement or estimate);

c. principal radionuclides (determined by measurement or estimate);

d. type of waste (e.g. , spent resin, compacted dry waste evaporator bottoms);

e. type of container (e.g. , LSA, Type A, Type B, Large Quantity),and

f. solidification agent (e.g., cement, urea formaldehyde).

BEAVER VALLEY - UNIT 1 3/4 11-22 PROPOSED WORDING

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4.1 The dose or dose commitment to MEllBER(S) 0F THE PUBLIC fran all facility releases is limited to 125 mrem to the total body or any organ (except the thyroid, VAich is limited to 675 mrem) for a calendar year.

APPLICABILITY: At all times.

ACTION:

a. With the c alculated dose from the release of radioactive materials in liqui /. or gaseous effluents exceeding twice the limits of Speci fica tions 3.11.1. 2. a , 3. l l . l . 2. b , 3. l l . 2. 2. a . 3. l l . 2. 2. b ,

3.ll. 2.3.a. or 3.ll. 2.3.b, prepare and submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 l defining the corrective action and limit the subsequent releases such that the dose or dose commitment to MEliBER(S) 0F THE PUBLIC is limited to 625 mrem to the total body or any organ (except thyroid, which is limited to 675 mrem) for a calendar year. This special report shall describe the steps to be taken or modifications necessary to prevent a recurrence.

Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR 190 Standard,

b. The provisions of Specification 3.0.3 and 3.0.4 are l not applicable.

SURVEILLANCE REQUIREMENTS , 4.11.4.1 Dose Calculations. Cummulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Speci ficati ons 3. ll . l . 2. a . 3. l l .1. 2. b, 3. l l . 2. 2. a . 3. l l . 2. 2. b ,

3. ll. 2. 3.a. and 3. ll. 2. 3.b, and in accordance with the ODCM.

BEAVER V/.LLEY - UNIT 1 3/4 11-23 PROPOSED WORDING

.- 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental l Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

(Deviations are permitted from the required sampling schedule if speciments are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.)

b. With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from l the end of affected calendar quarter a Special Report pursuant to Specification 6.9.2 which includes an evaluation of any release conditions, environmental factors or other aspects sich caused the limits of Table 3.12-2 to be exceeded. This report is not required .if the measured level of radioactivity was not the result of plant effluents; however,-in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

Concentration (l) , Concentration (2) + ... 2.1.0 Limit Level (1) Limit Level (2)

BEAVER VALLEY - UNIT 1 3/4 12-1 PROPOSED WORDING

s' RADIOIOGICAL ENVIRCtNAL MONI'IORHX3 3/4.12.2 IAND USE CENSUS LIMITING (INDITION EUR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.111, (Rev.1) July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

i APPLICABILITY: At all times.

ACI' ION:

a. With a land use census identifying a location (s) which yields a calculated dose or dose cTmitrent greater than the values currently being calculated in Specification 4.11.2.3, prepare and subnit to the Comnission within 20 days, pursuant to Specification 6.9.2, a Special Peport, which identifies the new location (s) .

b. With a land use census identifying a milch animal location (s) which yields a calculated dose or dcse ccumitrent (via the same exposure pathway) 20% greater than at a location frcm which scr;ples are currently being obtained in accordance with Specification 3.12.1, ,

prepare and subnit to the Ccmnission within 30 days, pursuant to specification 6.9.2, a Special Peport, which identifies the new l location. The new location shall be added to the radiological environmental tronitoring program within 30 days, if possible. The milk sa:Tling program shall include samples frcm the three active milch animal locations, having the higbest calculated dose or dose cm mitment. Any replaced location tray be deleted frem this r:cnitoring program after (Octcber 31) of the year in wtiich this land use census was conducted.

c. The provisions of Specification 3.0.3, and 3.0.4 are not applicable, a

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector,with the highest D/Q in lieu of the garden census.

BEAVER VALLEY - UNIT 1 3/4 12-10 PPCPOSED NOFDH!G

s'

< RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

APPLICABILITY: At all times, j ACTION: ;

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recur-rence to the Commission in the Annual Radiological Environmental Report.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS 4.12 3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report, t

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BEAVER VALLEY - UNIT 1 3/4 12-12 PROPOSED WORDING l

ADMINISTRATIVE CONTROLS ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the OSC Chairman to serve on a tenparary basis; however, no more than two alternates shall participate as voting members in OSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate.

000 RUM 6.5.1.5 A quorum of the OSC shall consist of the Chairman or his desig-nated alternate and four- members including alternates.

RESPONSIBILITIES 6.5.1.6 The OSC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety,

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety,

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the Offsite Review Committee.

f. Review of all REPORTABLE EVENTS. l

g. Review of facility operations to detect potential safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee.

BEAVER VALLEY - UNIT 1 6-6 PROPOSED WORDING

s' E

e AININISTPATIVE CONITOIS MEETING FRECUENCY 6.5.2.5 'Ihe ORC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum of ORC shall consist of the Chaiman or his designated alternate and at least 4 meubers including alternates. No more than a minority of the quorum shall have line responsioility for operation of the facility.

REVIEW 6.5.2.7 The ORC shall revies:

a. 'Ihe safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experiments ccrupleted under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, i b. Proposed changes to procedures, equiptent or systems which l involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or licenses,

e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

l l f. Significant operating abnormalities or deviations frcm normal l and expected perfomance of plant equipment that affect nuclear safety,

g. All REPORTABLE EVENTS. !

h. All recognized indications of an unanticipated deficiency in scme aspect of design or operation of safety-related structures, systems, or ccupenents,

i. Peports and meeting minutes of the OSC.

j. The results of the environmental monitoring program prior to submittal of the Annual Environmental Operating Peport.

BEAVER VAILEY UNIT 1 6-9 PROPOSED NORDING

,i ADMINISTRATIVE CONTROLS AUDITS (Continued)

AUTHORITY 6.5.2.9 The ORC shall report-to and advise the Vice President, Nuclear on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8. .

RECORDS 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated by the following:

a. Minutes of each ORC meeting shall be prepared for and approved by the ORC Chairman within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved, and forwarded-to the ORC Chairman within 14 days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be for-warded to the Vice President, Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.

d. The Vice President, Nuclear shall review all recommendations of the

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~0RC.

6.6 REPORTABLE EVENT ACTION C.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Canmission shall be notified and/or a report be submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the OSC, and the results of this review shall be submitted to the ORC and the Vice President, Nuclear.

PEAVER VALLEY - UNIT 1 6-11 PROPOSED WORDING L:

,i ADMINISTRATIVE CONTROLS

?

MONTriLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Manage-ment Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report.

6. 9.1. 7 DELETED 6.9.1.8 DELETED i

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I BEAVER VALLEY - UNIT 1 6-15 PROPOSED WORDING t

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ADMINISTRATIVE CONTROLS 6.9.1.9 DELETED l

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BEAVER VALLEY - UNIT 1 6-16/6-17 PROPOSED WORDING

s' 4 e ADMINISTRATIVE CONTROLS t 3

ANNUAL RADIOLOGICAL ENVIRONMENTAL REPORT l

6.9.1.10 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year and will e include reporting any deviations not reported under 6.9.2 with !

respect to the Radiological Effluent Technical Specifications. l

3. A single submittal may be made for a multiple unit site. The sub-mittal should combine those sections that are common to both units. ;

t L

)

I L

i i

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BEAVER VALLEY - UNIT 1 6-18

! PROPOSED WORDING ,

i I

o

,' ADMINISTRATIVE CONTROLS s.

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2.

e. Sealed source leakage in excess of limits, Specification 4.7.9.1.3.

f. Fire Detection Instrumentation, Specification 3.3.3.6.

g. Fire Suppression Systems, Specifications 3.7.14.1, 3.7.14.2 and 3.7.14.3 and 3.7.14.5.

h. Miscellaneous reporting requirements specified in the Action Statements for Radiological Effluent Technical Specifications.

i. Failure of the pressurizer PORT s, Specification 3.4.11.

j. Failure of the pressurizer safety valves, Specifications

3. 4.2 and 3. 4.3.

k. RCS specific activity, Specification 3.4.8.

1. Containment inspection report, Specification 4.6.1.6.2.

6.10 RECORD RETENTIN 6.10.1 The following records shall be retained for at least five (5) years:

'a. Pecords and legs of facility cperation covering time interval at each power level,

b. Records and 1 cgs of principal raintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORIABLE EVENTS. l

d. Fecords of surveillance activities, inspections and calibrations required by these Technical Specificatiens.

e. Pecords of reactor tests and experiments.

f. Records of changes made to Operating Procedures,

g. Records of radioactive shipnents.

h. Records of sealed source leak tests and results.

i. Pecords of annual physical inventory of all sealed source raterial of record.

BEAVER VALIIY - WIT 1 6-23 PROPOSED hCRDING

,i s

-o ATTACHMENT B i ,

SAFETY EVALUATION l Proposed Change Request No. 90 amends the Beaver Valley Power Station, Unit No. 1 Technical Specifications, Appendix A concerning revision to reporting requirements in accordance i with Generic Letter 83-43 and compliance with 10CFR50.72 and 50.73.

Description and Purpose of Change This change to-the Technical Specifications incorporates I the revisions addressed in Generic Letter 83-43. The revisions [

t reflect changes to the model Technical Specifications that "

incorporate the changes to the " Administrative Control" and

" Definition" sections and the other changes required to i conform to the revised reporting requirements. Additional '

changes to the reporting requirements applicable to, but not specifically addressed in, Generic. Letter 83-43 are described i as follows: r

, 1. Specifications 3.4.2, 3.4.3 and 3.4.11 have been revised to reflect reporting of safety valve and ,

i PORV failure as special reports under 6.9.2.

Reporting of safety valve and PORV failures was incorporated into specification 6.9.1.8.k by Amend- i ment 74 in response to Generic Letter 82-16. Since ,

6.9.1.8.k is being deleted, it was determined that the reporting should be listed as a special report.

2. Changes to 6.9.2: .

Item a. " Inservice Inspection Program Reviews, j Specification 4.4.10.1 and 4.4.10.2" has been f deleted since those surveillance requirements are e no longer in the Technical Specifications, having -

been deleted by Amendment 27.

Item g. has been revised to reference 3.7.14.5 to ,

reflect the reporting requirements for "Halon Systems" to be incorporated-into the Technical Specifications by Change No. 95 Item 1. " Failure of the Pressurizer PORVs, Speci-

. fication 3.4.11" was added to reflect the revised reporting requirement of 3.4.11.. ;

Item k. " Failure of the Pressurizer Safety Valves, 1 Specifications 3.4.2~and 3.4.3" was added to reflect reporting requirements of 3.4.2 and 3.4.3. f A. >

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b ATTACHMENT B SAFETY EVALUATION Page 2

2. Changes to 6.9.2 (continued)

Item 1. " Containment Inspection Report, Specifi-cation 4.6.1.6.2" was added. Since this is a special report, it was determined that the report should be listed in 6.9.2 Basis

1. Is the probability of an occurrence or the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the UFSAR increased?

No.

Reason: The changes are administrative in nature and reflect the revised reporting requirements of 10CFR50.72 and 50.73. The changes are not a safety concern and do not affect the UFSAR.

2. Is the probabil'ity for an accident or malfunction of a different type than previoualy evaluated in the UFSAR created? No.

Reason: The proposed changes-are administrative in nature and do not physically change plant safety-related systems, components or struc-tures, therefore, the changes will not create the possibility for a new type of accident or malfunction of a different type than any previously evaluated in the UFSAR.

3. Is the margin of safety as defined in the basis for any Technical Specification reduced? No.

Reason: The changes in the reporting requirements are administrative in nature. None of the systems or components will be physically changed or their function altered in any way. Therefore, the margin of safety inherent in the appli-cable bases will not be reduced.

'4. Based on the above, is an unreviewed safety question involved? No.

7 .-

[9 4

ATTACHMENT E SAFETY EVALUATION Page 3 Conclusion The changes are administrative in nature and do not involve physical changes to any plant safety-related systems, components or structures, will not increase the likelihood of a malfunction of safety-related equipment, increase the consequences of.an accident previously analyzed, nor create the possibility of a malfunction different than previously ,

evaluated in the UFSAR. The changes are being made in order to comply with the reporting requirements of 10CFR50.72 and 50.73 as specified in Generic Letter 83-43. The changes'are not a safety concern and do not affect the UFSAR.

Based on the considerations above, the proposed admin-istrative changes have been determined to be safe and do not involve an unreviewed safety question.

ML20084K273

Text

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