ML20203A226

Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design

ML20203A226
Person / Time
Site:	Point Beach
Issue date:	02/02/1999
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20203A214	List: ML20203A226 NPL-99-0064, Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement
References
NUDOCS 9902090314
Download: ML20203A226 (1)

Text

. .

]

.. . j l

1 1

,,, Safety analyses have been performed on the basis of a leakage rate of 0.40% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 60 psig. With this leakage rde and with minimum containment engineered safety systems for iodine removal in operation, i.e. one spray pump with sodium hydroxide addition.

the public exposure would be well below 10 CFR 100 values in the event of the design basis accident."

The safety analyses indicate that the containment leakage rates could be slightly in excess of 0.75% per day before a two-hour thyroid dose of 300R could be received at the site boundary.

The performance of periodic integrated leakage rate tests during piant life provide a current  ;

assessment of potential leakage from the containmer,t in case of an accident that would pressurize the interior of the containment. These t::sts are performed in accordance with Ine i Containment Leakage Rate Testing Program.

l Penodic visual and physical inspection of the containment tendons is the method to be used to determine loss of load-carTying capability because of wire breakage or deterioration. The tendon surveillance program specified in 15.4.4.11 is based on the recommendation of Regulatory Guide 1.35 Rev. 3. Containment tendon structural integrity was demonstrated for both units at the end of one, three and eight years following the initial containment structural integrity test.

The pre-stress lift-off test provides a direct measure of the load-carrying capability of the tendon. A deterioration of the corrosion preventive properties of the sheathing filler will be 1 indicated by a change in the physical appearance of the filler. If the surveillance program indicates, by extensive wire breakage, tendon stress-strain relations, or other abnormal conditions, that the pre-stressing tendons are not behaving as expected, the abnormal conditions will be subjected to an engineering analysis and evaluation in accordance with Specification 15.4.4.11.D to determine whether the condition could result in a significant adverse impact on the containment structural integrity. The specified acceptance critena are such as to alert attention to the situation well before the tendon load-carrying capability would deteriorate to a point that failure during a design basis accident might be possible. Thus, the cause of the incipient deterioration could be evaluated and corrective action studied without

, need to shut down the reactor. If the engineering evaluation determines that the abnormal l condition could result in a significant adverse impact on the containment structural integrity, an abnormal degradation situation will be declared and a report submitted to the NRC in accordance with the specifications.

1 l

l References l (1) FSAR Section 5.1.2[2, >

(2) FSAR Section 5.1.2 (3) FSAR Section 14.3.5 (4) FSAR Section 14.3.4 l (5) Deleted L g l (6) FSAR pages 5.1da.! nd 5.1g 9902090314 990202 ~

ADOC,K 05000266 PDR t P PDR ~

l Unit 1 - A;nendment No. 469,181 Unit 2 - Amendment No. 473,185 l 15.4.4-7