ML20204H168

Amend 118 to License NPF-1,changing Tech Specs to Delete Requirements for Shutdown If Primary Coolant Iodine Activity Limits Exceeded for 800 H in 12-month Period,Per Generic Ltr 85-19

ML20204H168
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/25/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204H165	List: ML20204H159 ML20204H168 ML20204H178
References
GL-85-19, NUDOCS 8608080023
Download: ML20204H168 (6)

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFI_C POWER AND LIGHT COMPANY C0CKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No NPF-1

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

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated April 9, 1986 complies with the standards and~ requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can'be conducted without endangering the nealth 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 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 regulations and all applicable requirements have been satisfied.

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- 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. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.118, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

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

FOR THE NUC AR y ORY COMMISSION 4

V ardajfDi vn . tor

- PWR Project Directo t No. 3 Division of PWR Lice ng-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance: July 25, 1986

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's,. . . . . ,d ATTACHMENT TO LICENSE AMENDMENT N0.118 TO FACILITY OPERATING LICENSE N0. NPF-1 DOCKET h0. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 4-19 3/4 4-19 B 3/4 4-4 8 3/4 4-4 6-15 6-15 I

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

a. $ 1.0 pCi/ gram DOSE EQUIVALENT I-131, and

b. 5 100/E SC1/ gram.

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

MODES 1, 2 and 3*

I a. With the specific activity of the primary coolant > 1.0 vCi/ gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable,

b. With the specific activity of the primary coolant > 1.0 pCi/ 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 Tavg < 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/E pCi/ gram, c.

be in HOT STANDBY with Tavg < 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

a. With the specific activity of the primary coolant > 1.0 pCi/grara DOSE EQUIVALENT I-131 or > 100/E vCi/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. The results of the analysis shall be submitted in the l

Annual Report and include the information required in Specification 6.').1.5.d.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

• With Tavg > 500*F.

i l TROJAN-UNIT 1 3/4 4-19 Amendment No. JJ0,118 i

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ADMINISTRATIVE CONTROLS cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months un'til all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their jssociated man rem exposure according to work and job functions , e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measure-ments. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific nejor work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

c. Documentation of all challenges to the pressurizer power oparcted relief valves (PORVs) or safety valves.

d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentra-tions; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant ex:eeded the radioiodine limit.

TROJAN-UNIT 1 6-15 Amendment No. 27, 97, 99, 79%,

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REACTOR COOLANT SYSTEM s

BASES The surveillance requirements provide adequate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not l exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed l

steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity

> 1.0 pCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon i which may occur following changes in THERMAL POWER. l Reducing Tavg to <500*F 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 relief valves.

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 if justified by the data obtained.

-- 3/4.4.9 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.

These cyclic loads are introduced by normal load transients, reactor '

trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 5.2 of the FSAR. During startup and shutdown, the rates of temperature and j pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy i the stress limits for cyclic operation.

i TROJAN-UNIT 1 B 3/4 4-4 Amendment No. 118 i

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