ML20100G426

Proposed Tech Spec Deleting cycle-specific Footnotes from Tech Spec Sections 4.4.5.1.3 & 3.4.6.2 & Table 4.7-2 Re Cycle 5 Refueling Outage & Operation

ML20100G426
Person / Time
Site:	Millstone
Issue date:	03/31/1985
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20100G423	List: B11499, Application for Amend to License DPR-65,deleting Footnotes from Tech Spec Sections 4.4.5.1.3 & 3.4.6.2 & Table 4.7-2 Re Cycle 5 Refueling Outage & Operation.Fee Paid ML20100G426
References
TAC-57423, TAC-57424, TAC-57425, TAC-57426, TAC-57427, NUDOCS 8504080243
Download: ML20100G426 (4)

Text

w a >

l Docket No. 50-336 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Deletion of Cycle 5 Specific Footnotes i

j March,1985 l[0%l$

P 6

_m,. ,.m. . . ,,r-.. - , , _ , - _ , - . ,, 9.#-..- , , ,--,,.

.. . - . -. __ ... - -~ _ _.. - _ - - - - - - .

f ..

W 4

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.3 Inspection Frequencies - The above required inservice inspections of 4 steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed af ter 6 Effective Full Power Months but within 24 calendar months of initial i criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months af ter j the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results f alling into the C-1 i category or if two consecutive inspections demonstrate that .

previously observed degradation has not continued and no additional

degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

b. If the results of the inservice inspection of a steam generator

conducted in accordance with Table 4.4-6 at 40 month intervals fall

!- into Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall

apply until the subsequent inspections satisfy the criteria of i Specification 4.4.5.1.3.a; the interval may then be extended to a

maximum of once per 40 months.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-6 during the shutdown subsequent to any of the following conditions:

l

1. Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds)in excess of the limits of Specification 3.4.6.2.

4 '

2. - A seismic occurrence greater than the Operating Basis Earthquake.

3. A loss-of-coolant accident requiring actuation of the engineered safeguards.

4. A main steam line or feedwater line break.

s i

MILLSTONE - UNIT 2 3/44-7 f

- , ., .m . . - , . _.-p., . - - - .%..,-_.m-- - - - - ,

, , _ , , . , . , ,, ,m g . - - , , , - - 3 .

,_7 -... ,.-.--. ., , --

s.. . s i

REACTOR COOLANT SYSTEM I

REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE,

c. 1 GPM total primary-to-secondary leakage through both steam l I

generators and 0.5 GPM through any one steam generator, and

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.

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

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in COLD I SHUTDOV:N within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

I j b. With any Reactor Coolant System leakage greater than any one of

.l the above limits, excluding PRESSURE BOUNDARY LEAKAGE, i reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in i COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

i l

SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a. Monitoring the containment atmosphere particulate radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l b. Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

c. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation except when j operating in the shutdown cooling mode. .

i I

i MILLSTONE - UNIT 2 3/44-9

, . . , - - - - - - , - , - - , n -.. , , r- ,,, --,-- . - - - -

~

e., s TABLE '4.7-2 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT MINIMUM AND ANALYSIS FREQUENCY

1. Gross Activity Determination 3 times per 7 days with a maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples.

'i 2. Isotopic Analysis for DOSE a) 1 per 31 days, when-i EQUIVALENT I-131 Concentration ever the gross activity determination indicates lodine concentrations greater than 10% of the allowable limit.

b) 1 per 6 months,

! whenever the gross

activity determination indicates lodine concentrations below 10% of the allowable limit.

e i

MILLSTONE - UNIT 2 3/47-8

. . . , . - , _ . _ . - _ , , - - . . . , ,. . - -