ML17256A946

Application for Amend to License DPR-18 Revising Requirements for RCS Iodine Activity

ML17256A946
Person / Time
Site:	Ginna
Issue date:	05/17/1982
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17256A945	List: ML17256A944 ML17256A946
References
NUDOCS 8205210336
Download: ML17256A946 (15)

Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION, In the Matter of )

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Rochester Gas and Electric Corporation ) Docket No 50 244 (R. E. Ginna Nuclear Power Plant, )

Unit No. 1) )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RG&E"), holder of Provisional Operating License No.

DPR-18, hereby requests that Sections 3.1.4 and 4.1 be revised in the Technical Specifications set forth in Appendix A to that license. This request for a change in Technical Specifications is submitted in response to a letter dated September 24, 1981 from Mr. Dennis M. Crutchfield, Chief, Operating Reactors Branch No. 5 regarding reactor coolant system iodine activity The proposed technical specification change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.

The proposed changes have been clearly identified as an NRC position in the NRC's Standard Technical Specifications for Westinghouse plants. Therefore a fee of $ 4,000 is required.

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WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached here to as Attachment A.

Rochester Gas and Electric Corporation By L. D. Whi e, Jr.

Executive Vice President Subscribed and sworn to before me on this l 7 day of May, 1982.

GARY L. EISS N RY PUBLIC, State of N. Y. Monroe Co.

hfy Commfssfon Expfres Marsh 30, 19~

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Attachment A 1 ~ Revise the Technical Specifications by replacing the following pages: 3.1-21,'.1-22, 3.1-23, 3.1-24, 4.1-8, 4.1-9, 4.1 2. Add page 4.1-12.

Maximum Coolant Activit S ecifications:

Whenever the reactor is critical or the reactor coolant average temperature is greater than 500oF:

a. The total specific activity of the reactor coolant shall not exceed 84/EpCi/gm, where E is the average beta and gamma energies per disintegration in Mev.

b. The I-131 equivalent of the iodine activity in the reactor coolant shall not exceed 1.0ju:i/gm.

cd The I-131 equivalent of the iodine activity on the secondary side of a steam generator shall not exceed 0 l~Ci/gm.

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If the limit of 3.1.4.l.a is exceeded, then be subcritical with reactor coolant average temperature less than 500 F within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

a ~ If the I-131 equivalent activity in the reactor coolant exceeds the limit of 3 '.4.l.b but is less than the allowable limit shown on Figure 3.1.4-1, 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 the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period.

If the I-131 equivalent activity in the reactor coolant exceeds the limit of 3.1.4 '.b for more than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6-month period, 3 '-21 Amendment No ~ 8,rX8

then prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days indicating the number of hours above this limit. The reactor may be taken critical or reactor coolant average temperature may be increased above a 500 F with the I-131 equivalent activity greater than the limit of 3.1.4.l.b as long as the provisions of this paragraph are met.

b. If the I-131 equivalent activity exceeds the limit of 3.1.4.1.b 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 exceeds the limit shown on Figure 3.1.4-1, be subcritical with reactor coolant average temperature less than 500oF within 8 hours.

c ~ If the I-131 equivalent activity exceeds the limit of 3.1.4.l.b, then perform sampling and analysis as required by Table 4.1-4, item 4a, until the activity is reduced to less than the limit of 3.1 4-1.b.

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3-1.4.4 If the limit of 3.1.4.1."c is exceeded, then be at hot shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and in cold shutdown within the following 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

Basis:

The total activity limit for the primary system corresponds to operation with the plant design basis of 1% fuel defects.

Radiation shielding and the radioactive waste disposal systems 3 '-22 Amendment No. g5

were designed for operation with 1% defects . The limit for secondary iodine activity is conservatively established with

,respect to the limits on primary system iodine activity and primary-to-secondary leakage (Specification 3.1.5.2). If the activity should exceed the specified limits following a power transient the major concern would be whether additional fuel defects had developed bringing the total to above 1% defects.

Appropriate action to be taken to bring the activity within specification include one or more of the following: gradual decrease in power to a lower base power, increase in letdown flow rate, and venting of the volume control tank gases to the gas decay tanks.

The specified activity limits provide protection to the public against the potential release of reactor coolant activity to the atmosphere, as demonstrated by the analysis of a steam generator tube'upture accident. (3)

The 500 F temperature in the specification corresponds at saturation to 681 psia, which is below the set point of the secondary side relief valves. Therefore, potential primary to secondary leakage at a temperature below 500 F can be contained by closing the steam line isolation valves.

References:

(1) FSAR Table 9.2-5 (2) FSAR Section 11.1.3 (3) Letter dated September 24, 1981 from Dennis M. Crutchfield, USNRC, to John E. Maier, RGSE.

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20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.1.4-1 I-131 Equivalent, Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity 1.0pCi/gram I-131 Equivalent 3.1-24

TABLE 4. 1-2

'MINIMUM FREQUENCIES POR EQUIPMENT AND SAMPLING TESTS FSAR Section Reference Test Free@en~

1. Reactor Coolant Chloride and Fluoride 3 times/week Chemistry Samples and at least every third day 5 times/week and at least. every second day except when below 250oF

2. Reactor Coolant Boron concentration Weekly Boron

3. Refueling Water Boron concentration Weekly Storage Tank Water Sample

4. Boric Acid Tank Boron concentration Twice/week

5. Control Rods Rod drop times of all After vessel head full length rods I

removal and at least once per 18 months (1)

6. Full Length Control Mvement of at least 10 Monthly Rod steps in any one direc-tion for any rod not fully inserted

7. Pressurizer Safety Set point Each Valves Refueling shutdawn

8. Main Steam Safety Set point Each 10 Valves Re fueling shutdawn

9. Containment Functioning Each Refueling Isolation Trip Shutdawn

10. Refueling System Functioning Prior to Refueling 9.4.5 Interlocks Operations ll. Service Wat,er System Functioning Each Refueling Shutdawn 9.5.5

, 12. Fire Protection Pump Auctioning Monthly 9.5.5 and Pawer Supply 4.1-8 Amendment No. p,pp,yy,yp

FSAR Section Reference Test Fre~en~c

13. Spray Additive Tank NaOH Concent. monthly

14. Accumulator Boron Concentration Bi-Monthly

15. Primary System Evaluate Daily

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16. Diesel Fuel Supply Fuel Inventory Daily 8.2.3

17. Spent Fuel Pit Boron Concentration monthly 9.5.5

18. Secondary Coolant Gross activity 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (2)(3)

Samples

19. Circulating Water Calibrate Each Refueling Flood Protection Shutdown Equignent Notes:

(1) Also required for specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods.

(2) Not required during a cold or refueling shutdown.

(3) An isotopic analysis for I-131 equivalent activity is required at least monthly whenever the gross activity determination indicates iodine concentration greater than lOS of the allowable limit but only once per 6 rmnths whenever the gross activity determination indicates iodine concentration below 10% of the allmrhle limit.

4.1-9 Amendment No . Q, gg, /gal

INTENTIONALLY BLANK 4.1-10

Attachment B The Technical Specification limits for reactor coolant system I-131 equivalent activity and for coolant activity sampling have been revised to be consistent with the NRC's Standard Technical Specifications for Westinghouse-designed plants. The activity limits are .conservative with respect to the assumptions used in the NRC's analysis of a steam generator tube rupture event which was provided to RGGE by letter dated September 24, 1981.

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'T i 0 TABLE 4.1-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Above cold shutdown (beta-gamma) (1) 2 ~ Isotopic Analysis for Dose 1 per 14 days Above 5t reactor power Equivalent I-131 Concentra-tion 3 Radiochemical for E 1 per 6 months (3) Above 5% reactor power Determination (2)

Isotopic Analysis for a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever As required by Specificati'on Iodine Including I-131, the I-131 equivalent 3.1.4.3.c*

I-133, and I-135 activity exceeds the limit of 3.1 4.l.b

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b) One sample between 2 and 6 Hot shutdown or above hours following a reactor power change exceeding 15 per-cent within a 1-hour period (1) A gross radioactivity analysis shall consist of the quantitative measurement of the total radio-activity of the primary coolant in units~i/gm. The total primary coolant activity shall be the sum of the degassed beta-gamma activity and the total of all identified gaseous activit'5 minutes after the primary system is sampled.

(2) A radiochemical analysis shall consist of the quantitative measurement of the activity for each radionuclide which is identified in the primary coolant 15 minutes after the primary system is sampled. The activities for the individual isotopes shall be used in the determination of E.

(3) Sample to be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

• Except at refueling shutdown, sampling shall be continued until the activity of the reactor coolant system is restored to within its limits.

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