ML20072S675

Amend 90 to License DPR-22,involving Several Improvements to Radiological Effluents Portion of Plant TSs

ML20072S675
Person / Time
Site:	Monticello
Issue date:	09/07/1994
From:	Marsh L Office of Nuclear Reactor Regulation
To:
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ML20072S677	List: ML20072S675 ML20072S679
References
NUDOCS 9409140194
Download: ML20072S675 (10)

Text

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S UNITED STATES i'

i NUCLEAR R"ULATORY COMMISSION g

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WASHINGTON, D.C. 2055!4 001 NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-22 1.

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

A.

The application for amendment by Northern States Power Company (the licensee) dated August 10, 1993, complies with the standards and requirements of the Atomic. Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter 1:

B.

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

There is reasonable assurance (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 Commission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows:

9409140194 940907 PDR ADOCK 05000263 P

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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 90, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

l 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Speci ficatior.s Date of Issuance:

September 7, 1994 i

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l ATTACHMENT TO LICENSE AMENDMENT N0, 90 EACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

REMOVE INSERT 51 51 195 195 198 198 198d 198d 198i 1981 198j 198j 198t 198t i

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Table 3.2.1 - Continued NOTES:

(1)

For Groups 1, 2 and 3 there shall be two operable or tripped trip systems for each function. A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.

For Groups 4, 5 and Reactor Pressure Interlocks there shall be two operable or tripped trip systems for each function.

(2)

For Groups 1, 2 and 3, upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated as follows:

l (a)

With one re channel inoperable in one or more trip functions, place the inoperable channel (s) quired instrument or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b)

With more than one instrument channel inoperable for one or more trip functions, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c)

Place the plant under the specified required conditions using normal operating procedures.

For Groups 4, 5 and Reactor Pressure Interlocks upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to:

(a)

Satisfy the requirements by placing appropriate channels or systems in the tripped condition.

(b)

Place the plant under the specified required conditions using normal operating procedures.

(3)

Low pressure in main steam line only need to be available in the RUN position.

(4)

All instrument channels are shared by both trip systems.

(5)

May be bypassed when necessary only by closing the manual containment isolation valves during purging for contalnment inerting or de-inerting.

Verification of the eypass condition shall be noted in the control room log.

Also, need not be operable when primary contitua?nt integrity is not required.

O Required conditions when minimum conditions for operation are not satisfied.

A.

Group 1 isolation valves closed.

B.

Reactor Power on IRM range or below and reactor in startup, refuel, or shutdown mode.

C.

Isolation Valves closed for:

Shutdown Cooling System, and Reactor llead Cooling Line.

D.

Comply with Condition C. above.

E.

Isolation Valves closed for:

Reactor Cleanup System.

F.

IIPCI steam line isolated.

(See specification 3.5 for additional requirements.)

G.

RCIC steam line isolated.

3.2/4.2 51 Amendment No. 34, 90

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.

Liquid Radwaste System 3.

Liquid Radwaste System a.

The liquid radwaste treatment system a.

Doses due to liquid releases shall be shall be used to reduce the radioactive projected at least once each month in accordance with the ODCM.

materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (Figure 3.8.1) when averaged over one month would exceed 0.06 mrem to the total body or 0.2 mrem to any

organ, b.

With radioactive liquid waste being discharge without treatment in excess of the limit in (a) above, within 30 days submit to the Commission a special report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) to be taken to restore equipment to operable status, and 3.

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

195 3.8/4.8 Amendment No. 16, M, 90

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 2.

Dose from Noble Gases 2.

Dose from Noble Cases Cumulative dose contributions for the a.

The air dose due to noble gases a.

released in gaseous effluents current calendar quarter and year from from the site (Figure 3.8.2) noble gases in gaseous effluents shall shall be limited to the following be determined in accordance with the values:

ODCM monthly.

1.

During any calendar quarter, to $5 mrad for gamma radiation and $10 mrad for beta radiation, and 2.

During any calendar year, to $10 mrad for gamma radiation and $20 mrad for beta radiation.

b.

With the calculated air dose from radio-active noble gases in gaseous effluent exceeding any of the above limits, within 30 days submit to the Commission a special report which identifies the cause(s) for exceeding the limits (s) and defines the corrective actions taken to reduce the releases and the proposed corrective eccions to be taken to assure che subsequent releases will be within the above limits.

198 3.8/4.8 Amendment No. F6, A6, 90

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 5.

Main Condenser Offgas Activity 5.

Main Condenser Offgas Activity The gross gamma radioactivity of noble gases from The gross gamma radioactivity release the main condenser air ejector shall be determined a.

rate measured at the stream jet air be within the limit specified in 3.8.B.S.a at t

ejector shall be limited to $2.6 x 10, the following times by performing an isotopic uci/sec following a 30-minute decay.

analysis of a representative sample of gases:

b.

When the limit in (a) above is 1.

Once every month.

exceeded, restore the gross gamma radioactivity release rate to within 2.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an increase in the c utinuous monitor reading of 50% after the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at f ct ring out increases due to power level.

least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

the activity of radioactive material in gaseous form removed from the main condenser shall be continuously 6.

Containment Venting and Purging monitored by the steam jet air ejector monitors in accordance wich Table a.

Except for inerting operations following 3.8.2.

startup and deinerting prior to shutdown, the containment shall be determined to be aligned for venting or purging throu-h the Standby d.

The steam jet air ejector monitors Gas Treatment System within k hours prior to shall be set to automatically terminate offgas flow within 30 minutes at the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during venting or purging of the containment limit established in Specification above cold shutdown.

3.8.B.S.a.

b.

Prior to containment purging, the sampling 6.

Containment Venting and Purging and analysis requirements of Table 4.B.4 shall be met.

a.

Except for inerting operations following startup and deinerting prior to shutdown, containment venting and purging above cold shutdown shall be via the 2-inch bypass flow path using the Standby Cas Treatment System.

b.

Containment inerting following startup and deinerting prior to shutdown shall be via the Reactor Buildicg plenum and vent.

198d 3.8/4.8 Amendment No. M, M, 90

TABLE 3.8.1 - RADIOACTIVE ' 'MUID EFFLUENT MONITORINC INSTRUMENTATION t age i of 2)

Minimum Instrument Channels Applicability Action if Minimum Channels not operable Operable Liquid Radwaste Effluent 1

During Release Liquid radwaste releases may continue for up to 14 Line Cross Radioactivity of Liquid days provided that prior to initiating a release:

Monitor Radwaste a.

At least two independent samples are analyzed in accordance with Specification 4.8.A.l.b b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

Liquid Radwaste Effluent 1

During Release Liquid radwaste releases via this pathway may Line Flow Instrument of Liquid continue for up to 30 days provided the flow rate is Radwaste estimated at least once every four hours during actual releases. Pump curves may be used to estimate flow.

Discharge Canal Flow During Release Effluent releases via this pathway may continue for Measurement:

of Liquid up to 30 days provided the flow rate is estimated at cle Mode 1

Radwaste least once every four hours during actual releases.

- Open Cy/ Helper Cycle Mode

- Closed 1

Pump curves may be used to estimate flow.

Discharge Canal Cross 1

At all times Effluent releases may continue for up to 30 days Radioactivity Monitor

• provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a grab sample shall be collected and analyzed for gross beta at an LLD of 10-' pCi/ml or gamma isotopic for principle gamma emitters at an LLD of 5.0 X 10-'

s41/ml Service Water DischarSe 1

At all times Service water discharge may continue for up to 30 Pipe Gross Radioactivity days provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a grab sample shall be collected and analyzed for gross beta Monitor

• at an LLD of 10 pCi/ml or gamma isotopic for 7

principle gamma emitters at an LLD of 3.0 X 10~'

s41/ml

- Indicates monitor provided with automatic alarm 1981-3.8/3.8 Amendment No. PJ, ACT, 90

TABLE 3.8.1 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 cf 2)

Minimum Instrument Channels Applicability Action if Minimum Channels not operable operable Turbine Building Normal 1

At all times Liquid sump releases may continue for up to 30 days Sump Monitor

• provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a grab sample shall be collected and analyzed for gross beta at an LLD of 10' pCi/ml or gamma isotopic for principle gamma emitters at an LLD of 5.0 X 10-7 uCi/ml Level Monitors for 1

When tanks are Liquid additions to a tank may continue for up to 30 Temporary Outdoor Tanks in use days provided the tank liquid level is estimated Holding Radioactive Liquid during all liquid additions.

• - Indicates monitor provided with automatic alare 3.8/4.8 198j Amendment No. Pf, 90

TABLE 4.8.4

- RADIOACTIVE CASEOUS WASTE S AMPLING AND ANALYSIS PROGRAM (continued)

(Page 2 of 2)

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%

a.

probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

Note (a) of Table 4.8.3 is applicable.

b.

Crab samples taken at the discharge of the plant stack and reactor building vent are generally below minimum detectable levels for most nuclides with existing analytical equipment.

For this reason, isotopic analysis data, corrected for holdup time, for samples taken at the steam jet air ejector may be used to calculate noble gas ratios Whenever the steady state radioiodine concentration is 6teater than 10 percent of the limit of Specification c.

3.6.C.1, daily sampling of reactor coolant for radioactive iodines of I-131 through I-135 is required.

Whenever a change of 25% or more in calculated Dose Equivalent I-131 is detected under these conditions, the iodine and particulate collection devices for all release points shall be removed and analyzed daily until it is shown that a pattern exists which can be used to predict the release rate.

Sampling may then revert When samples collected for one day are analyzed, the corresponding LLD's may be increased by a to week 1. 10.

Samples shall be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal factor o d.

To be representative of the average quantities and concentrations of radioactive materials in particulate form in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent streams.

The principal gamma emitters for which the LLD specification will apply are exclusively the follouing e.

radio-nuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, and Ce-144 for This list does co-58, Co-60, 2n-65,hese nuclides areMo-99, Cs-134, Cs-137, Ce-141,d and reported. particulate emissions.Other peaks which are measurable not mean that only t to be detecte identifiable, together with the above nuclides, shall also be identified and reported.

f.

Nuclides which are below the LIE for the analyses shall be re orted as "less than" the LLD of the nuclide and should not be reported as being present at the LLD level or that nuclide. The "less than" values shall not be used in the required dose calculations. When unusual circumstances result in LLD's higher than reported, the reasons shall be documented in the semiannual effluent report.

g.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period sampled.

h.

H2 analysis shall not be required prior to purging if the limits of 3.8.B.1 are satisfied for other nuclides.

However, the IP analysis shall be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after sampling.

1.

In lieu of grab samples, continuous monitoring with bi-weekly analysis using silica-jel samplers may be provided 198t 3.8/4.8 Amendment No. 35, 90

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