ML20213D639

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Proposed Tech Specs,Reducing Reporting Requirements for Primary Coolant Iodine Spikes to Annually & Eliminating Action Statement Requiring Plant Shutdown If Coolant Iodine Activity Limits Exceed 10% Total Yearly Operating Time
ML20213D639
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/29/1986
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20213D331 List:
References
GL-85-19, TAC-63349, NUDOCS 8611120168
Download: ML20213D639 (7)
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Docket No. 50-336 B12236-

-Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Reporting Requirements on Primary Coolant Iodine Spikes October,1986 8611120168 861029 ADOCK0500g6 PDR

REACTOR COOIMrr SYSTEM l

i SPECIFIC ACTIVITY l

LIMITING CONDITION FOR OPERATION 3.4.8 he specific activity of the primary coolant shall be limited to:

a.

f 1.0 pCi/ gram DOSE EQUIVALENT I-131, and b.

f 100/E pCi/ gram.

+

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

ACTION:

MODES 1, 2 ar.d 3*:

a.

With the specific activity of the primary coolant >1.0 4

JACi/ gram DOSE EQUIVALENr 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 />. W e provisions of Specification 3.0.4 are not applicable.

b.

With the specific activity of the prinnary coolant >1.0 4

yCi/ gram DOSE EQUIVALI!Nr 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 Ier STANDBY with T'"

<515 F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the specific activity of the primary coolant >100/E c.

pCi/ gram, be in Ier STANDBY with T,,, <515*F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

MODES 1, 2, 3, 4 and 5:

d.

With the specific activity of the primary coolant >1.0 pCi/ gram DOSE EQUIVALDFr I-131 or >100/Ili C1/ gram, perform l

the sampling and analysis requirements of item 4 a) of Table 4.4-2 until the specific activity of the primary coolant is 4

restored to within its limits.

  • With T,,, > 515* F.

I MILLSTONE - UNIT 2 3/4 4-13 I

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REACTOR C00LAlff SYSTDI SURVEILIANCE REQUIRDENTS l

4.4.8 2he specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-2.

1 MILLSTONE - IMIT 2 3/4 4-14

REAC'IOR COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY

'Ihe. limitations on Reactor Coolant System contaminants ensure that corrosion of the Reactor Coolant System is minimized and reduce the potential for Reactor coolant System leakage or failure due to stress corrosion. Maintaining the concentrations of the contaminants within the Steady State Limits shown on Table 3.4-1 provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. 'Ihe associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.

Corrosion studies show that operation may be continued with contaminant concentration levels in excess o'f the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System.

'Ihe time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

h surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY h 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 exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM and a concurrent loss of offsite electrical power.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity >l.0 p ci/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, acccannodates possible iodine spiking phenomenon which may occur following changes in 'IHERMAL POWER.

i MILLS'IONE - IMIT 2 B 3/4 4-4 i

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' ADMINISTRATIVE CQf1'HOLS 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 comunencement of commercial power operation, or (3) 9 months following initial' criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e.,

initial 1

criticality, completion of startup test program, and resumption or commencement of comunercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

AteRIAL 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. The initial report shall be prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

1 A tabulation on an annual basis of the number of station, a.

utility and other personnel (including contractors) receiving man-rem exposure according to work and job functions,pciated exposures greater than 100 mrenVyr and their ass 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 measurements.

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 major work functions.

b.

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

1 A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are cosanon to all units at the station.

2 This tabulation supplements the requirements of 6 20.407 of 10CFR Part 20.

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MILLSTONE - UNIT 2 6-18

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ADMINISTRATIVE CONTROLS c.

S e results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.

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following information shall be included:

(1) Reactor power j

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 sagle 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 the limit.

Each result should include date and time of sampling and the radiciodine concentrations; (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) he time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

-MILLSTONE - UNIT 2 6-18a

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,,.4 ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis'to the Director, Office of Resource Management, U.S. Nuclear Regulatory.. Commission, Washington, D.C. 20555, with a copy to -

the Regional Administrator, Region I, U.S. Nuclear Regulatory Commission, no later than the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

i c.

Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1.

d.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e.

Fire Detection Instrumentation, Specifications 3.3.3.7.

~ f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

g.

RCS Overpressure Mitigation, Specification 3.4.9.3 h.

Radiological Effluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.4.

1.

+ Degradation of containment structure, Specification 4.6.1.6.4.

J.

Steam Generation Tube Inspection, Specification 4.4.5.1.5.

l MILLSTONE - UNIT 2 6-19 l

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