ML19208D861
| ML19208D861 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/30/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML16294A398 | List: |
| References | |
| NUDOCS 7910010215 | |
| Download: ML19208D861 (4) | |
Text
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DOCKET NO. 50-213 ATTACHMENT HADDAM NECK PLANT PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS
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SEPTEMBER, 1979 7 910 010,U5 1058 139
be performed locally at a pressure of not less than 40 psig, using halogen gas detection, soap bubbles, pressure decay, or other methods of equivalent sensitivity.
Isolation valves shall also be tested for operability.
1.
Containment penetrations with resilient seal gaskets, or sealant compounds, 2.
Air lock assembly and equipment door seals.
3.
Fuel transfer tube.
4.
Isolation valves on lines penetrating containment.
5.
Other containment components, beside II-A.1, 2, 3, which required leak repair following any integrated leakage rate test to meet maximum allowable leakage limit.
B.
Acceptance Criterion The sum of the leakage from all penetrations and isolation valves shall not exceed L.
p C.
Corrective Action If at any time it is determined that II-B is exceeded, the reactor shall be shut down and depressurized until repairs are effected and leakage is within sp;cified limits.
D.
Test Frequency Individual penetrations shall be tested at a frequency of at least every 12 months wherever practical with the following exceptions:
1.
The containment equipment hatch and the fuel transfer tube shall be tested at each refueling shutdown or, after each time they are used if that be sooner.
2.
Isolation valves, essential for plant operation shall be tested during shutdowns when the reactor is depressurized if the test has not been performed within the previous 12 months.
3.
The personnel air-lock assembly shall be leak tested at not less than 40 psig at least once every 6 months. If the airlock is opened during the interval between these tests, and containment integrity is required, the air-lock door seals shall be tested at not less than 10 psig within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first of a series of openings.
The 10 psig test results shall be conservatively ex-trapolated to a leakage rate at 40 psig.
1053 140 4-7
e A continuous monitoring system will be used to monitor containment air leakage whenever the reactor is critical.
Experience with this system (3) indicates that low leakage rates (0.01%/ day) can be detected within one month. The use of the continuous monitoring system is the basis for not including the one year interval, as suggested in (4), in the integrated leakage test frequency of Specification I-D.
The two and three year intcrvals between successive tests were selected from a guideline established by the AEC staff (4).
The objectives of the airlock leak testing requirements are (1) that the six month test will provide an integrated leakage rate for the entire airlock assembly, including electrical and mechanical penetrations, hinge assemblies, welded connections, and other potential leakage paths; and (2) that the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> test will provide a means of assuring that the door seals have not been damaged or seated improperly during airlock use.
The six-month air-lock Icakage test complies fully with the surveillance requirements of section III.D.2 of 10 CFR 50
, Appendix J. The interim 72-hour reduced pressure test is an approved exemption from these require-ments based on the recommendations of reference (6).
The recirculation system includes high pressure charging system and a low pressure residual heat removal system. The high pressure protion will not be used except for small breaks in the main coolant system (less than 4" diameter).
For such small breaks there would be no fuel damage and leakage of radioactivity from the recirculation system would be negligible (0.25 R maximum dose at site boundary for 2 gpm leakage). However, for larger breaks where only the low pressure portion of the recirculation system would be used, some fuel damage could occur and a limit on such leakage is necessary.
For six liters per hour leakage the calculated doses are less than 2% of the 10 CFR 100 limits.
In addition, leakage up to six liters per hour is not indicative of seal failure unless this leakage is increasing.
Therefore, the leak rate from the residual heat removal pump seals will be monitored for at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> whenever it excecds 2 liters / hours.
If the leak rate does not decrease or stabilize before it reaches 6 liters /hr the pro-visions of Technical Specification 3.14 will apply.
The air filtration portion of the air recirculation system is a passive engineered safeguard, to be used only in the event of an incident involving a rupture of the reactor coolant system. Hence, the charcoal should have a long useful lifetime.
The filter frames that house the charcoal are stainless steel and should also last indefinitely. However, the tests specfied in Section IV of this specification will be performed to verify that this is in fact the case.
1053 141 4-10
References:
(1) FDSA - Section 3.6 (2)
FDSA - Section 10.4 (3) YAEC-1005-An Evaluation of the Yankee Vapor Container Leakage Monitoring System.
(4) Technical Safety Guide - Reactor Containment Leakage Testing and Surveillance Requirement.
(5) Amendment'12 to CY License Application.
(6) Attachment A to USNRC letter to D. C. Switzer, dated March 11, 1977.
)Q 1 t-4-10a