ML19341D055
| ML19341D055 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/11/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341D056 | List: |
| References | |
| NUDOCS 8103040778 | |
| Download: ML19341D055 (6) | |
Text
f] ' fog UNITED STATES g
,9; NUCLEAR REGULATORY COMMISSION y
g 5
E WASHINGTON, D. C. 205S5 -
t,.... /
JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 52 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Jersey Central Power and Light Company (the licensee) dated October 18,1977 and October 6,1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.
l l
i l
8103040778
.. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Provisional License No. DPR-16 is hereby amended to read as follows.
3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k-Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changer to the Technical Speci fi cations Date of Issuance: February 11, 1981 0
l f
.A-
~
n v
r e
ATTACHMFNT TO LICENSE AMENDMENT NO. 52 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by captioned amendment number and contain vertical lines indicating the area of ccange.
PAGES 4.5-5a 4.5-5b*
4.5.ga 1
i There is no change to the provisions contained on this page; i' is included for format and pagination purposes only.
i
- ~ ~
(.
I
4.5-Sa j
pressure of not less than 1.0 psi, the differential' pressure f
decay rate snall not exceed the equivalent of air flow through a 2-inch orifice.
J.
Reactor Building i
1.
Secondary containment capability tests shall be conducted after isolating the reactor building and placing either Standby Gas 3.
Treatment System filter train in operation.
'2.
'Ihe tests shall be performed at least once per operati ig cycle and shall demonstrate the capability to maintain a 1/4 inch of water.
vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cfm.
1, A secondary containment capability test snall be conducted at each refueling outage prior to refueling.
4.
Tne results of the secondary containment capability tests shall be in the subject of a sumary technical report which can be included in tne reports specified in Section 6.
l:
i K.
Standby Gas Treatment System 1.
The capability of each' Standby Gas Treatment System circuit shall be demonstrated by:
a.
At least once per 18 months, after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> or operation, and following significant painting, fire, or chemical release in the reactor building during operation of the Standby Gas Treatment System by verifying that:
(1)- The charcoal absorbers remove 2.
99% of a halogenated hydrocarbon refrigerant test gas and the HEPA filters remove 2 99% of the DOP in a cold DOP test when tested in accordance with ANS! N510-1975.
(2) Results of laboratory carbon sample analysis show a 90%
radioactive metay1 icdine removal efficiency when tested in accordance with ASTM D 3803-79
( 30* C, 95% relative I
humidity).
b.
At least once per 18 months by demonstrating:
'l Amendment No. M, 52 w--'e-=eg*S2,y---e9-
-m-+W y-yp-9-,y-y+35--W-
,,,-9,9
,W9s,,,,,,
4.5-Sb
.I (1) Tnat tne pressure drop across a IIcPA filter is equal to or less tnan tne maximum allowable pressure drop indicateo in Figure 4.5.1.
(2) Itle inlet neater is capable of at least 10.9 h input.
(3) Operation witn a total tiow witnin 10% of design flow.
c.
At least once per 30 days on a STACGERt.D TEST BASIS by operating eacn circuit for a minimtan of 10 nours.
Anytime the IIcPA filter canx or tne cnarcoal adsorbers ' nave a.
=
ueen partially.or completely replaced, tne test for 4.5.n'.1.a will be performeo prior to returning tne system to OPERABLE:
xAIC.i.
t.
Autunatte tuitiation of esca etrcuit every 18 nontns.
4 t
}
i i
i i
e i
i i
l Amendment No. J4, 52 i
i I
4.5-9a chamber pressure cust not exceed a rate equivalent to the rate of air flow from the drywell to the suppression chamber through a 2-inch orifice.
In the event the rate of change of pressure exceeds this value, then the source of leakage will be identified and climanated before power operation is resumed.
The drywell-suppression chamber vacuum breakers are exercised monthly and immediately following termination of discharge of steam into the suppres-sion chamber.
This monitoring of valve operability is intended to assure that valve operability and position indication system performance does net degrade between refueling inspections.
When a vacuum breaker valve is exercised through an opening-closing cycle, the position indicating lights are designed to function as follows:
Full Closed 2 Green - On (Closed to 0.10" open) 2 Red - Off Open 0.10" 2 Green - Off (0.10" open to full open) 2 Red - On During each refueling outage, four suppression chamber-drywell vacuum breakers will be inspected to assure components have not deteriorated.
Since valve internals are designed for a 40-year lifetime, an inspection program which cycles through all valves in about one-tenth of the design lifetime is extremely conservative.
The alarm systems for the vacuum breakers will be calibrated during each refueling outage.
This frequency is based on experience and engineering; judgement.
Initiating reactor building isolation and operation of the standby gas treatment system to maintain a 1/4 inch of water vacuum, tests the operation of the reactor building isolation valves, leakage tightness of the r'eactor building and performance of the standby gas treatment system.
Checking the initiating sensors and associated trip channels demonstrates the capability for automatic actuation.
Perforcing the reactor building in leakage test prior to refueling demonstrates secondary containment capability prior to extensive fuel handling operations associated with the outage.
Verifying the efficiency and operation of charcoal filters once per 18 months gives sufficient confidence of standby gas treatment system performance capability.
A charcoal filter efficiency of 99~ for halogen removal is adequate.
l The in-place testing of charcoal filters is performed using Freon-112*
which is injected into the system upstream of the charcoal filters.
l Measurement of the Freon concentration upstream and downstream of the I
charcoal filters is made using a gas chromatograph.
The ratio of the inlet and outlet concentratians gives an overall indication of the leak tightness.
- Trade name of E. I. duPont de Nemours & Company Amendment No. 52