ML20080R030
| ML20080R030 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/05/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080R021 | List: |
| References | |
| NUDOCS 8310170311 | |
| Download: ML20080R030 (2) | |
Text
-
~
=- ~
f UN!TED STATES
~'
r e& jf i
NUCLEAR REGULATORY COMMISSION i
usmucron. o. c. 20sss
- \\.db/;!
~
SAFETY EVALUATION BY TNE OFIICE OF NUCLEAR REACTOR REGULATION SUPPORTING AliEMDMENT NO. 87 TO FACILITY OPERATING LICENSE 'NO. DPR-50 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENRSYLVANIA ELECTRIC COMPANY GPU NUCLEAR COMPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 DOCKET NO. 50-289 Introduction By letter dated January 26, 1982, GPU Nuclear Corporation (the licensee) submitted a proposed license amendment to add Technical Specifications defining the applicable modes of operation, actions to be taken for system inoperability, and surveillance requirements for the hydrogen recombiner system at TMI-1.
The hydrogen recombiner system and the dedicated penetra-tion for the external recombiners have been evaluated by the NRC staff, and the results of that evaluation are included in the "TMI-l Restart" report, NUREG-0680, dated June 1980. 'The dedicated penetration and hydrogen recombiner system were found acceptable in NUREG-0680 except for an evaluation by the. licensee that potential leakage and discharge to the atmosphere of the Intermediate Building air used for recombiner cooling will not result in offsite dose releases in excess of 10 CFR Part 100 limits. This Safety Evaluation, therefore, is limited to the review of the potential releases due l
to recombiner cooling leakage and to the Technical Specifications as adopted i
from the Stancard Technical Specifications for Babcock & Wilcox reactors, l
Evaluation The licensee's analysis of the potential leakage and discharge to the atmosphere of the Intermediate Building air used for recombiner cooling nas been documented in the licensee's " Report in Response to NRC Staff Recommended Requirements for Restart of Three Mile Island Nuclear Station, Unit 1" four volumes. The specific reference is Supplement 1, Part 2, Question 91b.
In the report, the licensee
[
states that the hydrogen recombiner system is an engineered safeguards welded piping system with the exception of the recombiner connection and flow element I
i flanges. After installation of the redundant recombiner, the piping system shall L
be pneumatically tested to demonstrate the integrity of the piping system.
f
[
The addition of any possible leakage from the closed piping system will be an insignificant contribution to the total containment leakage and will not affect the accident dose evaluation previously made for the plant.
l We have reviewed the licensee's report and agree that the establishment of the system's integrity and demonstration that any leakage is within acceptable limits j
are sufficient. The licensee's analysis is therefore acceptable.
i 8310170311 831005 PDR ADOCK 05000 l
P
. :: L ::
=L r ~::
~~~T
~L
--L---l
e 2-In the proposed Technical Specifications,, the licensee described the testing
~
procedures for the hydrogen reco.mbiner :and the associated control system.
These testing procedures provide for the following:
(a) A recombiner functional test once per 92 days; and (b) The following surveillance every 18 months: channel calibration of the recombiner's instrumentation,
- visual examination of the heater, heater functional test and heater electrical circuit integrity test.
The proposed testing procedures for the hydrogen recombiner and the associated control system are consistent with those established for other engineered safety features. Therefore, we. conclude that the proposed test procedures for the hydrogen recombiners are acceptable and that the associated proposed change to the Technical Specifications should be approved.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignifi-cant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5 (d)(4), that an environmental statement, or negative declaration and enviro'nmental impact appraisal need not be prepared in connection with the iss.uance of tnis amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public j
will not be endangered by operation,in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: October 5,1983 The following NRC personnel have contributed to this Safety Evaluation:
P. Hearn, D. Wigginton.
9 l
r.-
C 1 _ J--
-T
- - I n -- ::