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Amend 204 to License DPR-50,revising TMI-I Which Decreases Max Allowable Dose Equivalent I-131 Limit in Reactor Primary Coolant from 1.0 Uci/Gm to 0.35 Uci/Gm
	ML20211G850
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Site:	Crane
Issue date:	10/02/1997
From:	Eaton R; NRC (Affiliation Not Assigned)
To:	;
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ML20211G853	List: ML20211G850; ML20211G856;
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	NUDOCS 9710030274
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goat:g g-t UNITED STATES NUCLEAR RECULATCRY COMMISSl2N WASHINGTON, D.C. 30006-4001 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. !i0-289 JF " MILE ISLAND NUCLEAR STATION. UNIT NO. 1 xMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 204 License No. DPR-50 4

1.

The Nuclear Regulatory Commission (the Comission or NRC) has found that:

A.

The application for amendment by GPU Nuclear Corporation, et al.

(the licensee) dated August 14, 1997, as upplemented September 9, 19 and 24, 1997, 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 I; 1

B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that suh activities will be conducted in compliance with the Comission'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 Comission's regulctions and all applicable requirements have been satisfied.

sNb 6t'l (00 yo 9710030274 971002 PDR ADOCK 05000209 P

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- 2.

Accc-dingly, 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-50 is hereby amended to read as follows:

(2)

Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 204, are brebv incorporated in the l

license. GPU Nuclear Corporation

-,1 operate the facility in accardance with the Technical Spectfications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/wHf Ronald B. Ecton, Acting Director l

Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Techr.ical Specificatio,'.s Date of Issuance:

October 2,1997

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I ATTACHMENT TO LICENSE AMENDMENT NO. 204 3

FACILI17 OPERATING' LICENSE NO. DPR-50 DOCKET NO.~50-289

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Replace the following pages of the Appendix A Technical Specifications, with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3-8 3-8 3-9 3-9 i

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3-9b 3-9b 4-9 4-9 i

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3.1.4 REACTOR COOLANT SYSTEM ACTIVITY 3.1.4.1-LIMITING CONDITION FOR OPERATION The specific activity of the primary coolant shall be limited to:

ss than or equal to 0.35 m!crocurie/ gram DOSE EQUIVALENT }.131, and l

s.

x

b. Less than or equal to 1005 microcuries/ gram

3.1.4.3 APPLICABILITY: at all times except refueling 1

i 3.1.43 - ACTION:

i l

MODES: Power Operation, Start Up, Hot Standby

a. - With the specific activity of the primary coolant greater than 0.35 microcurie / gram DOSE l

EQUIVALENT l 131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ** during one continuous time interval or exceeding the limit line shown on Figure 3.1 2a, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Power operation may continue when DOSE EQUIVALENT l-131 is below l

0.35 microcurie / gram.

I

b. With the specific activity of the primary coolant greater than100lE microcuries/ gram be in at least HOT SilUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Power operation may continue when primary coolant activity is less than 100/E suicrocuries/ gram.

MODES: At all times except refueling.

With the specific activity of the primarycoolant greater than 0.35 microcurie / gram *2OSE l

- c.

EQUIVAl.ENT l-131 or greater than 100Emicrocuries/ gram perform the sampling and analysis requirements of Table 4.1 3 ur,t!! the rpsific activity of the primary coole.nt is restored to within its limits Baan The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will be well within the Part 100 limit following a s'eam generator tube ruptua accident or steam line break accident with postulated accident induced steam generator tube leakage in conjunction with an assumed steady state primary-to sen,ndary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent limits based on a parametric evaluation by the NRC of typical site locations.' These values are conservative, in that the specific site parameters of TMI 1, such as site boundary, location and meteorological conditions were not considered in this evaluation.

s

E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than lodines, with halflives greater than 15 minutes, v

making up at least 95% of the total non iodine sctivity in the coolant.

- The time period begins from the time the sample is taken.

3-8 Amendment No. UMr, JFI. 204

4 De ACTION statement permitting POWER OPERATION to continue for limited time periods with the L

. primary coolant's specific activity greater than 0.35 microcurie / gram DOSE EQUIVALENT l 131, but l

. within the allowable limit shown on Figure 3.1 2s, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.

Proceeding to HOT SHUTDOWN prevents the release of activity should a steam generator tube rupture

- since the saturation pressure of the primary coolant is below'the lift pressure of the atmospheric steam reliefvalves.

.The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible ifjustified by the data obtained.

The NRC staff has performed a generic analysis of airborne radiation released via the Reactor Building Purge isolation Valves. The dose contribution due to the radiation contained in the air and steam released through the purge isolation valves prior to closure was found to be acceptable provided that the.

requirements of Specifications 3.1.4.1,3.1.4.2 and 3.1.4.3 are met.

3-9 Amendment No. lad, kd, 204

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c' L-20 39 40 to 80 70 to DC 100 F1RCENT OF RATih THERuAL power FIGURE 3.1-2a Dose equivalent 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER (with the Primary Coolant Specific Activity >0.35 Ci/ gram Dose Equivalent 1-131).

Amendment No. d, }(7, 204 3-9b 1

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TABLE 4.1-3 i

MINIMUM SAMPLING FREQUENCY i

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Item Check Freauency Zo"

1. Reactor Coolant a.

Specific Activity Determination to compare to At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during POWER f

N the 100/E pCi/gm limit OPERATION, ilOT STANDBY, START-U P, and 180T t

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SilUTDOWN.

b. Isotopic Analysis for DOSE EQUIVALENT i)

I per 14 days during power operations.

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I-131 Concentration f

g ii) One Sample between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a i

TilERMAL POWER change exceeding 15% of the RATED TilERMAL POWER within a one hour period during power operation, start-up and Ixt standby.

iii) # Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , w%er the si.ecific activity exceeds 0.35 pCi/ gram DOSE EQUIVALENT I-131 I

t or 1001 E pCi/ gram during all modes but refueling.

e Radiochemical for 5 Dete mination I per 6 months

during power operation c.

d. Chemistry (CI, F and 0 )

5 times / week when T is greater than 200*F.

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c.

Boron concentration 2 times / week f.

Tritium Radioactivity Monthly 2.

Borated Water Storage Boron concentration Weekly and after each makeup when reactor coolant.

Tank Water Sample system pressure is greater than 300 psig or T is greater m

than 200*F.

3. Core Flooding Tank Boron concentration Monthly and after each makeup when RCS pressure is Water Sample greater than 700 psig..

ML20211G850

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