ML20100J167

Amend 84 to License DPR-66,revising Tech Specs Re 10CFR50.72 Immediate LER Notification Requirements for Operating Nuclear Power Reactors

ML20100J167
Person / Time
Site:	Beaver Valley
Issue date:	11/27/1984
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20100J169	List: ML20100J167 ML20100J183
References
TAC-55010, NUDOCS 8412100240
Download: ML20100J167 (37)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION o

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! j WASHINGTON, D. C. 20555 4 h DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No.84 License No. DPR-66 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

.The application ~ for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated May 2,1984, as supplemented by letter dated August 30, 1984, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Commission's rules and regulations set forth in '10 CFR Chapter I;'

B.

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

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications a's indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

8412100240 841127

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, (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendc.ent No. 84, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective on issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f

St$ven arg ef Operating Reactors Branch #1 Division of. Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 27, 1984 1

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-334

. Revise Appendix A as follows:

. Remove Pages

' Insert Pages 1-2 1-2 3/4 1-20 3/4 1-20 3/4 3-53 3/4 3-53 3/4 3-59 3/4 3-59 3/4 4-6 3/4 4-6 3/4 4-10b 3/4 4-10b B3/4 4-2a

_B3/4 4-2a 3/4 4-18 3/4 4-18 3/4 4-29 3/4 4-29 3/4 6-10 3/4 6-10 3/4 7-35 3/4 7-35 3/4 7-41 3/4 7-41 3/4 11-1 3/4 11-1 3/4 11-6 3/4 11-6 3/4 11-8 3/4 11-8 3/4 11-10 3/4 11-10 3/4 11-11 3/4 11-11 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-18 3/4 11-18 3/4 11-20 3/4 11-20 3/4 11-21 3/4 11-21 3/4 11-22 3/4 11-22 3/4 11-23 3/4 11-23 3/4 12-1 3/4 12-1 3/4 12-10 3/4 12-10 3/4 12-12 3/4 12-12 6-6 6-6 6-9 6-9 6-11 6-11 6-13 6-13 6-15 6-15 6-16 6-16/6-17 6-17 6-18 6-18 6-23 6-23 4

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

GliTAlf.MEid INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

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

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a.

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

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' All equipment' hatches are closed and sealed.

1.8.3 Each air lock is OPERABLE p[rsuant to Specification 3.6.1.3.,

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M' l.8.4 The ccntainment leakage rate fare within the' limits of Specification 3.6.1.2.

CHANNEL CALIBRATION l.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the

.-channel output'such that i,t responds with the necessary range and accu-racy to known values of the parameter which the channel monitors. The 1

CHANilEL CALIBRATI0fl shall encompass the entire channel including.the sensor and alarm and/or trip functions, and shall include the CHANNEL FUtiCTI0ilAL TEST.

The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. '

CHAflNEL CHECK 4

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.

- EEMER VALLEY - UtlIT 1 1-2 Amendment flo. 84

E.CN QM SYSIS POSITION INDIC JTICN SYSTDIS-OPEPATING LDIITING CONDITION MR OPERATICN 3.1.3.2 The shutdcwn and control rod position indicatica system shall be OPERABLE at follcws:

Group De: rand Counter (1),1 per group Individual analog rod position instrument channel, 1 per rod + 12 steps (1) accuracy (3)

Antaratic 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.. The provisions of Specification 3.0.4 are not applicable to this' monitor (3).

I1)

During the first hour following rod motion, the group demand counter is the primary indicator of precise rod positicn infor '

mation, with the analog channels displaying general rod movement information. For power levels below 50%, a 1-hour thermal soak time is allowed before the analog channels are required to per-form within the specified accuracy.,e qqq.

(2)

For pcwer levels below 50% a one hour thermal soak time is allowed. Therefore, if a Rod Position Deviation Monitor alarm clears itself within this hcur, the alarm is considered invalid.

J (3)

Malfuncticns of the group demand counters, analcq RPI or Rod Deviation Fonitor, providing no actual rod misalignment e.dsted during the malfunction, shall be reported in the monthly operating report.

EEAVER VAtl5l UNIT 1 3/4 1-20 Amendment No. 84

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INSTRUMEllTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING C0"DITION 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-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 (00CM).

"11 APPLICABILITY: 'During releases ihrough' the flow path.

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ACTION:

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With a radioactive liquid effluent monitoring instrumentation a.

channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release

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of radioactive liquid effluents monitored by'sthe affected

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channel or correct the' ala'rm/ trip setpoint.E J

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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 why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and

- l 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHAllNEL CHECK, SOURCE CHECX, CHANilEL CALIBRATION and CHAtlNEL FUtlCTIO!1AL TEST operations at the frequencies shown in Table 4.3-12.

EAVER VALLEY - U'f!T 1 2/4 3-53 Amendment flo. 84

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f INSTRU'iENTATION RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10' The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm /.

trip setpoints set to ensure that the ifmits of 3.11.2.1 are not exceeded.

The alann/ trip setpoints of the radiation monitoring channels shall be detennined in accordance with the Offsite Oose Calculation-Manual (0DCM).

APPLICABILITY: During releases through the flow path.

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ACTION:

With a radioactive gaseous process or effluent monitoring a.

instrumentation channel alarm / trip setpoint less conservativ'e than a value which will ensure that the limits of 3.11.2.1.

are met,. immediately suspend the release of radioactivi gaseous effluents monitored by the affected channel or correct the alarm / trip setpoint.

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b.

With..one or more, radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-13 or conservatively reduce the alarm setpoint.' Exert a best effort to return the channel to l

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.

SURVEILLANCE REQUIRB4ENTS 4.3.3.10 Each radioactive gaseous 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 4.3-13.

i SEAVER VALLEY - UNIT 1 3/4: 3-59 Amendment No. 84

REACTDR' COOLANT SYSTEM SAFETYVALhES-OPERATING LIMITING CONDITION FOR OPERATION 3.". 3

~ All pressurizer code safety valves shall be OPERABLE with a lif t setting of 2485 PSIG 1%.

APPLICABILITY: Modes 1, 2, hnd 3 ACTION:

With one pressurizer code safety valve inoperable, either restore the a.

inoperable ~ valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12. hours.

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SURVEILLANCE REQUIREMENTS 4.4.3 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2485 PSIG 1%, in accordance with Specification 4.0.5.

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BEAVER VALLEY - UNIT 1 3/4 4-6 Amendment No. 84 1

z REACTOR COOLANT-SYSTEM SURVEILLANCE REQUIREMENTS (Continued) l c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported to the Commission pursuant to Spec:.fication 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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9 BEAVER VALLEY - UNIT 1 3/4 4-10b Amendment No. 84

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REACTOR COOLANT SYSTE!!

, BASES The Surveillance Requirements fo inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will. be maintained.

The progra:n 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 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 e

provides a means of characterizing the. nature and cause of any tube deg-radation so that corrective measures can be taken.

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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 extenf 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 ~dning normal operation and by postulated accidents. Operating plant have demonstrated that primary-to-snondary 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 Speciff-cation 4.4.5.4.a is 40% of the tube nominal wall thickness.

Steam generator tube inspections'of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Ilhenever 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 - U!!IT 1 B 3/4 4-2a Amendment No. 84 w.

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y c-D: ACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specif'.: activity of the primary coolant shall be limited to:

a.

<1.0 uCi/ gram DOSE EQUIVALENT I-131, and b.

<100/E pCi/ gram.

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

ACTION.

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MODES 1, 2.and 3*

With the specific activity of the primary coolant > 1.0 pCi/ gram a.

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time.. The provisions of Specification 3.0.4 are not applicable.

M b.

With the specific activity of the primary coolant >l.0 uCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T,yg <500'F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With the specific activity of the primary coolant > 100/EuCi/ gram, c.

be in H0T STANDBY with T,yg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1, 2, 3, 4 and 5 With the specific activity of__the primary coolant >1.0 uCi/ gram a.

DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-12 until the specific activity of the primary coolant is restored to within its limits.

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 Tavg ' 500*F BEAVER VALLEY - UNIT 1 3/4 4-18 : Amendment No. 84

REACTOR C00LANT. SYSTEM SURVEILLANCE REOUIREMENTS (Continued) a.

At the' first refueling outage, dye penetrant inspections shall

'be performed on all six reacter vessel' nozzles and volumetric inspections shall be perferred en at least two noz:les in the same manner as that conducted in the baseline inspection.

b.

At the second refueling outage, a dye penetrant examination shall be perforred 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 the 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 performsd on the three outlet nozzle to safe end welds from the inside diameter.

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t EEAVER VALLEY - UNIT 1 3/4 4-29 Amendment No. 84 4

CONTAILMENT SYSTEMS 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 4.6.1.6.1.

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-leakag#"e rate test (reprence

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Specification 4.6.1 2) by:

m-b a.

a visual inspection of the accessibTe 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'-

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

c.

a visual inspection of the dome area prior to each Type A contain-ment leakage rate test to insure the integrity of the protective 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 abnonnal 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 requirerents of this specification, and the detailed report shall be submitted pursuant to Specification 6.9.2 within 90 days after ccepletion. This l

rerort 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.

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U.' : 7 1 3/4 6-10 Amendment No. 84

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; Two high pressure pumps, each with a capacity of 2500 gpm, a.

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 OPERA 8LE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alann device on each sprinkler, hose standpipe or spray system riser required to be OPERABLE per Specifications

3. 7.14. 2 an~d.3. 7.14. 4. :

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APPLICABILITY: At all times.,

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With one pump inoperable, restore the inoperable equipment to a.

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 outlin'ing the pla to provide for the loss of redurdans and procedures to be used ncy 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 2..

Submit a Special Report in accordance with Specification 6.9. 2; a)

By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b)

Confirmed by telegraph, mailgram or facsimile trans-mission no later than the first working day following the event, and SEAVER VALLEY - UNIT 1 3/4 7-35 Amendment No. 84

PLANT SYSTEMS LOW PRESSURE C0; SYSTEtt LIMITING CONDITION FOR OPERATION 3.7.14.3 The 70 ton low pressure C0 system serving the following areas shallbeOPERA5LEwithaminimumlev81of30%andaminimumpressureof 275 psig in the associated storage tank, a.

Cable Tray Mezzanine

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b.

Cable Vaults c.

Diesel Generator Room APPLICA8ILITYi Whenever equipment in the low pressure CO2 protected areas is required to be OPERABLE.

ACTION:

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With the above required low pressure C0 system inoperable,.es-tablish a continuous fire watch with balkup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore e

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 2 ystem shall be demonstrated s

OPERABLE:

a.

At kast once per 7 days by verifying CO storage tank level,and 2

pressure, and b.

At least once per 18 nionths by verifying:

1.

The :,ystem 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".

~,IAVIE VALLEY - UNIT i 3/4 7-41 Amendment No. 84 n

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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 th'e 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 entrained noble gases, the concentration shall be limited to 2 x 10- pCi/ml total activity.

APPLICACILITY: At all times.

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ACTION:

a.

With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; imediately restore concentration within the above limits, and.,_

b.

Submit a Special Report to the Commission within 30 days in accordance with Specification 6.9.2.~,:. A "gy - 9 G's

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c.

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 4.11-1*.

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 specifications 3.11.1.1.

p Radioactive liquid discharges are nomally via batch modes.

Turbine.

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

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I EEAVER VALLEY - UNIT 1 3/4 11-1 Amendment flo. 84 l

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RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION l

3. l l.l. 2 The dose or dose commitment to HENBER(S) 0F THE PUBLIC FROM radioactive materials in liquid effluents released from the site (see 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.

and b.

During any calendar par'to less than or equ.a1 to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

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ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any' "ofL the above.lfaitsTprepare and -

t submit to the Commission within 30 days, pursuant to l

. Specification 6.9.2, a Special Report sich identifies the cause(s) for exceeding the limit (s) and defines the corrective 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 Ifmits.

(This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking, water supplies with regard to the requirements of 40 CFR 141 Safe Drinking Water Act)

• b.

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

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

BEAVER VALLEY - UNIT 1 3/4 11-6 Amendment No. 84

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RADI0 ACTIVE EFFLUENTS

_LICUID 1'ASTE TREATP.ENT LIMITING CONDITION OF OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be used to reduce the radioactivt materials in each liquid waste batch prior to its discharge 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 Ifmits specified, prepare and submit to the Commission within 30

'l days pursuant to Specification 6.9.2 a Sp'ect,a1 Report which_ includes the following information:

.. 1.

Identification of the inoperable equipment or subsystems d*-T*"

and the reason for inoperability,i*a' -

Action (s) taken 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.

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BEAVER VALLEY - UNIT 1 3/4 11-8 Amendment No. 84 J

RADI0 ACTIVE EFFLUENTS LICU!D HOLOUP TMKS LIlIITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of -

' the followidg tanks shall be *1 frc.ited to :s 10 curies, excluding '

tritium and dissolved or entrained noble gases.

a.

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

BR-TK-68 (Primary Water Storage Tank) c.

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

LW-TK-78 (SteamGereratorDrainTank) e.

Miscellaneous temporary outside radioactive liquid.

storage tanks.

.a.

APPi.ICA8Ii.!TY: At all times.

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ACTION:.

4

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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 of activities planned and/or taken to reduce the contents to within the specified ifmits.

t i

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not appItcable.

I SURVEILLANCE REQUIREMENTS i

i 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.

i SEAVER VALLEY - Uti!T 1 3/4 11-10 Amendment flo 84 D

0

m.

+ '

RADI0 ACTIVE EFFLUENTS 3/4.11.2 G*SEOUS E :LUEflTS DbSERATE LIMITING C0flDITION 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 from the site shall be limited to the following values:

The dose rate limit for noble gases shall be g500 mrem /yr a.

to the total body and $.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 be11500 mrem /yr to any organ.

APPLICABILITY: ht all times, su 4 <.

ACTION:

,w

'?

" 'a.

With the do~se rate (s) exceedinh7th'eibove limits,'immediately decrease the release rate to comply with the above Ifmit(s), and '

b.

Submit a Special Report.to 'the Commission within 30 days pursuant to Specification 6.9.2.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

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

4 SEAVER VALLEY - UllIT 1 3/4 fl-11 Amendment flo. 84

p.

I RADI0 ACTIVE EFFLUENTS DOSE, NOBLE 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.

4 b.

During any calendar year, to 110 mrad for gamma radiation and

, 620 mrad for beta radiation.

c APPLICABILITY: At all times.

' ACTION:

~..

.s a.

With the calcu. lated 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

~

s:

Specification 6.9.2, a Special-Rep' ort vAich identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to ~ reduce the releases' and the pr.oposed 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.

I SURVEILLANCE REQUIREMENTS l

I l

4.11. 2. 2 Dose calculations. Cumulative dose contributions shall l

be determined in accordance with the ODCil at least once every 31 days.

l i

BEAVER VALLEY - UNIT 1 3/4 11-15 Amendment No. 84 i

l

RADI0 ACTIVE EFFLUENTS DOSE, RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORff, AND s

RADIONUCLIDES OTHER THAN 110BLE GASES LIMITING CONDITION FOR OPERATION 3.11. 2.3 The dose to MEMBER (S) 0F THE PUBLIC from radiofodines 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 17.5 mrem to any organ, and b.

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

cti.

APPLICABILITY:

At all times.

s

~

. <. A.

ACTION:-

,.c.

With the calculated dose frmn the release of radiotodines, r-a.

radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half lives greater uMi'

' 'than 8 days, in gaseous effluents ~ exceeding'any of the above limits, c.

prepare and submit to the Commission within 30 days, pursuant to l

Specification 6.9.2, a Special Re3 ort, which identifies the cause(s) for.

exceeding the limit and defines t1e corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the abov.e limits, b.

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

l SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.

Cumulative dose contributions shall be determined in accorcance witn the ODCM at least once every 31 days.

BEAVER VALLEY - UNIT 1 3/4 11-16 Amendment flo. 84 l

' RADI0 ACTIVE EFFLUENTS GASE0US RADUASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11. 2.4 The Gaseous Radwaste. 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 mead 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 gaseoes 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:

-e r-Qith gaseous waste being discharged without treatment and in~ exces.s a.

of the _above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which' includes the following informatio,,n:

..sg.;ggg-

_. _.. m. w. -

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 ODCil.

BEAVER VALLEY - UNIT 1 3/4 11-18 Amendment No. 84

[

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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 s.52000 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce' the tank contents to within the limit, and b'.

Submit a Special' Report to the Commission within 30 days pursuant to Speciff. 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....,.J.

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c.

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

SURVEILLANCE REOUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in each gas storage tank shall be detennined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank when the Waste Gas Decay Tank Monitor (RM-GW-101) is not operable, 4.11. 2.5. 2 The Waste Gas Decay Tank Monitor (RM-GW-101) operability shall be detennined in accordance with Table 4.3-13 unless sampling pursuant to 4.11.2.5.1 is being conducted.

e BEAVER VALLEY - UNIT 1 3/4 11-20 Amendment No. 84

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.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste 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 <4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

.. d..

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.

i:

~

c.

The provisions of Specifications 3.0.3 and3.0.4arenotapplicable.l SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentrations of oxygen in the waste gas h'oldup system shall be detennined to be within the above limits by contin-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-ment.

SEAVER VALLEY - UNIT 1 3 /4 1.1-21 Amendment No. 84

~-

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 procedures 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 provisi ns of Specificat' ions 3.0.3 and 3.0.4 'are l

not applicable.

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' r* % _

v;c SURVEILLANCE REQOIREMENTS IN"' '

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4.11.3.1.1 Prior to' shipment; solidification shall be verified in accordance with Station Operating Procedures.

4.11.3.1.2 Reports.

The semi-annual Radioactive Effluent Release Report in Specification 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 (determined 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);

type 'of container (e.g., LSA, Type A Type B, Large e.

Quantity),and f.

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

DEAVER VALLEY - UNIT 1 3/4 l'l-22 Amendment No, 84

RADI0 ACTIVE EFFLUENTS

-3/a.11.4 -TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4.1.The dose or dose commitment to MEMBER (S) 0F THE PUBLIC from all facility releases is limited to 125 mrem to the total body or any organ (except the thyrc04, which is limited to 675 mrem) for a--

calendar year.

APPLICABILITY: At all times.

ACTION:

~

a.

With the calculated dose'from the~ release of radioactive materials in liquid or gaseous effluents exceeding twice the lfmits of Specifications 3.11.1. 2.a. 3.11.1. 2.b 3.ll. L 2.a. 3.ll. 2. 2.b, 3.11. 2.3.a. or 3.11. 2.3.b, prepare and submit a Special Report to '

l the Commission within 30 days pursuant to Specification 6.9.2 defining the correctiv'e action and limit the subse such that the dose or dose commitment to MEMBER (S)quent releases 0F THE PUBLIC is limited-to 125 mrem to the total body or any organ E"

.(except thyroid, which is limited. to f75 mrem) for.a calendar -

~

year.

This 'special report 'shall" describe the steps to be ~

~

~

taken gor modifications necessary to prevent a recurrence.

Otherwise, obtain a variance from the Commission to pennit 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

- Specifications 3.11.1. 2.a. 3.11.1. 2.b, 3.11. 2. 2.a. 3.11. 2. 2.b, 3.11. 2. 3.a and 3.11,2. 3.b, and in accordance with the ODCM.

SEAVER VALLEY - UNIT 1 3/4 11-23 Amendment No. 84 e

e

[

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

=

3/4.12.1 MO*!ITORING 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 Report, a description of the reasons for not conducting the progrant 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, i

seasonal. unavailability, or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action pricr to the end of the next sampling period.),

g;

-- : b.

With the level of radioactivity.jn an environmentalisampling

.W 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 i

quarter, prepare and submit to the Commission within 30 days from l -

l the end of affected calendar quarter a Special Report pur~ tant to l

Specification 6.9.2 which includes:an evaluation of any release l

conditions, environmental factors or other aspects which caused l

the limits of Table 3.12-2 to be exceeded.

This report is not l

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:

l Concentration (1)

Concentration (2) 3

+....>.1.0 Limit Level (1)

Limit Level (2)

BEAVER VALLEY - UNIT 1 3/4 12-1 Amendment No. 84

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RADIGIrGICAL EWIramIAL IONTIORING i

3/4.12.2. IAND USS CD' SUS LIMITING CONDITION EOR OPERATIN 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 neteorological 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 pr

• ing fresh leafy vegetables in each of the' 16 meteorological sectors within a distance of three miles.)

APPLICABILITY: At all times.-

-y.

ACTION:

'a.

With a land use census identifying ~a" location (s) which yields a r=1m1=ted dose or dose cmmitznent greater than the values currently being <almlated in Specification 4.11.2.3~, prepare and subnit to the owniasiat within 30 days, pursuant to Specification 6.9.2, a

., cc.a.

t=< 4=1 Report, which identifies ~the'new location (s). 4

- - e: ~, -

b.

With a land use census identifying a milch animal location (s) which yields a < almlated dose or dose cmmit=ent (via the same exposure pathway) 20% greater than at a location frcm which sarples are currently being obtained in accordance with-Specificatien 3.12.1, prepare and subnit to the Camission within 30 days, pursuant to Specification 6.9.2, a Special Report, which identifies the new location. The new location shall be added to the radiological envirormental nenitoring program within 30 days,. if possible. The-milk sampling program shall include samples frcm the three active milch animal locations, having the highest calculated dose or dose cmmitment. Any replaced location may be deleted frcm this monitoring program after (Cchhr 31) of the year in which this land use census was conducted.

c.

'Ihe previsions of Specification 3.0.3, and 3.0.4 are not applicable.

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

'BETNER W.LLEY - WIT 1 3/4 12-10 Amendment No. 84 e

e-

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 -INTERLABORATORY COMPARISON 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.

, ACTION:

f a.

With analyses not being performed as required above.

' report the corre~ctive actions taken to prevent a recur-rence to the Commission in the Annual Radio. logical

^

Environmental Report..

b. - The1 provisions of Specification 3.0.3y and 3.0.4 are not applicable.

l

. s,xey

~

~

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 Environaental Report.

b BEAVER VALLEY - UNIT 1 3/4 12-12 Amendment No. 84

ADMINISTRATIVE CONTROLS ILTERNATES

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

iiEETING FREQUi;'CY 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.

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

a,..

RESPONSIBILITIES 6.5.1.6 The.0SC shaill be respons.ible for:

a.

Review of 1) all procedures' required by Specification 6.8 and changes thereto, 2) any other. proposed' procedures or changes thereto as detemined by the Plant Superintendent to affect g

nuclear safety.;.

-!$gg$ - -

r_

b.

Review of all prop ~osed tests and ' experiments that affect nuclear safety, c.

Review of all proposed chan'ges to Appendix "A" Technical Specifications, d.

Review of all proposed changes or modifications to plant systems.

or equipment that affect nuclear safety.

I.

Investigation of all violations of the Technical Spec'ifications e.

including the preparation and forwarding of reports ccvering evaluation and recommendat. ions to prevent recurrence to the r

Manager of Nuclear Operations and to the Chaiman of the Offsite i

Review Committee..

l

)

f.

Review of all REPORTABLE EVENTS.

j g.

Review of facility operations to detect potential safety hazards.

h.

Perfomance of special reviews, investigations or analyses and reports thereon as requested by the Chaiman of the Offsite Review Committee.

l 5EAVER VALLEY - UNIT 1 6-6 Amendment No. 84

l

'.I m Isr e E CCt.TaCLS M=.urU FRECUB'CY 6.5.2.5 ne ORC shall reet at least once pr calendar quarter during the initial year of facility cperation. following fuel loading and at least once.per 'ix renths thereafter.

O MM 6.5.2.6 A quorun of ORC shall consist of the Chairman or his designated alternate and at least 4 me:rbers including alternates. No rore than a rinority of the quartra shall have line responsibility for cgration of the facility.

REVIEW 6.5.2.7. % e ORC shall review:,..

=c. :.

a.-

2e safety evaluations for 1) changes to procedures, equip-.

m ment or systems and 2) tests or experiments empleted under-

,the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

e-;

b.

Proposed' changes to procedures, equipnent or systems which involve an unreviewed safety qs stion as defined in Section

,.,e

- ' 50.59, 10 CFR. - -

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. g79; p a

c.

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

l d.

Proposed changes.in Technical Specifications or licenses, e.

Violations of applicable statutes, codes, regulations, orders, l

Technical Specifications, license requirements, or of internal l

procedures or instructions having nuclear safety significance.

f.

Significant ccerating abnorralities or deviations frc:a norral l

and exmetied perforrance of plant equianent that affect nuclear l

safety.

1 g.

All m.rQuaBLE EMIS.

h.

All recognired indicaticns of an unanticipated deficiency in sme aspect of design or cperation of safety-related structures, syste:rs, or ccuponents.

l l

i.

Feports and reeting minutes of the OSC.

j.

The results of the environmental monitoring program prior to submittal of the Annual Envircn:nental Operating Peport.

EE.'!Eo '.G.UEI UNIT 1 6-9 Amendment no. 84 L

ADMINISTRATIVE CONTROLS AUDITS (Continued) 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:

Minutes of each ORC meeting shall be prepared for and approved by the a.

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..

, g; 1.-

v...

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded 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 ORC.

6.6 REPORTABLE EVENT ACTION

1. .'~ M 3.U h i h _

6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified in accordance with 10 CFR 50.72 and/or

? port be submitted pursuant to' the requirements of Section 50.73 to s

luCFR 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.

~ BEAVER VALLEY. UNIT 1 6-11 Amendment No. 84 e

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ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

Theintentbftheoriginalprocedureisnotaltered.

a.

b.

The change is ap3 roved by two (2) members of the plant management staff, at least one (l? of whom holds a Senior Reactor Operator's License on the unit affe;ted.

The clange is documented, reviewed by the OSC and approved by the Plant c.~

Superintendent within 14 days of implementation.

I 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS l

6.9.1 In addition to the applicable 1 reporting requirements of Title 10, Code ~

of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office, of Inspection and Enforcement unless otherwise noted.

~

W STARTUP REPORTS

~

4~

y 6.9.1.1 A summary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating license (2) amendment to 9

the license involving a planned increase.in power level, (3) installation of-s c

M fuel that has a different design or has been manufactured by a diffe' rent fuel n

supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design. predictions and specifications. Any

~

corrective actions that were required to obtain satisfactory operation shall also be described.

Any aditional specific details requested in, license conditions based on other comitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or-f commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If f rc: Startup Report does not cover all three events (i.e.. initial criticality, completion of startu and resumption or commencement of commercial power operation)p test program,

, supplementary reports shall be submitted at least every three months until all three events have been completed.

BEAVER VALLEY - UNIT 1 6-13 Amendment No. 84

ADMINISTRATIVE CONTROLS i;0NTHLY OPERATING RdPORT_

.6.9.1.6 Routine reports of operating statistics and shutdown experience shall ba submitted 'on a monthly basis to the Director, Office of Manage -

ment Information and Program Control, U.S. Nuclear Regulatory Commission, yashington, 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

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6. 9.1. 8 DELETED

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BE' AVER VALLEY - UNIT 1 6-15 Amendment No. 84

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ADMINISTRATIVE. CONTROLS 6.9.1.9

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BEAVER VALLEY - UNIT 1 6.-16/6-17 Amendment No. 84 I

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ADMINISTRATIVE' CONTROLS 3

ANNUAL ~ RADIOLOGICAL ENVIRONMENTAL REPORT 6.9.1.10 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shal1 be submitted prior to May 1 of each year and will include reporting any deviations not reported under 6.9.2 with l

respect to the Radiological Effluent Technical Specifications.

3 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.

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-BEAVER VALLEY - UNIT 1 6-18

. Amendment No. 84

f

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' ADMINISTRATIVE CONTROLS a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable _ Seismic Monitoring Instrumentation, Specification 3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation.

-c.

Specification 3.3.3.4.

d.

Seis-aic 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, Soecification 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.

7 Ofi h.

Miscellaneous reporting' requirementis'specified in the Action Statements for Radiological Effluent Technical Specifications.

i.

RCS specific activity, Specification 3.4.8.

Containment inspection report, Specification 4.6.1.6.2.

j qi.7 6.10 RECORD RETENTION The following records shall be rethdiffor at l' ast fiNI5)

MieE '

6.~10.1 e

years:

a.

Records and logs of facility operation covering time interval at each power ' level, b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

h.

Records of sealed source leak tests and results.

i.

Records of annual physical inventory of all sealed source material of record.

BEAVER VALLEY - UNIT 1 6-?3 Amendment No. 84

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