ML17156A168
| ML17156A168 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/23/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17156A167 | List: |
| References | |
| NUDOCS 8504300016 | |
| Download: ML17156A168 (5) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION AMENDMEN N.
NPF-14 SUS UEHANN STEAM ELECTRIC STATI N
UNIT 1 DOCKET NO. 50-387 Introduction By letter dated November 13, 1984 the licensee requested changes to the TS to support the required modifications to comply with License Condition 2.C.(17)
(b)(2) which reads as follows:
"Prior to startup following the first refu'cling outage, PP&L shall incorporate the following additional modifications into the scram discharge volume system:
(2) Diverse and redundant SDV instrumentation for each instrumented
- volume, including both delta pressure sensors and float sensors."
Evaluation This amendment was submitted as a result of modifications to the Scr'am Discharge Volume (SDV) and associated equipment, accomplished in order to comply with License Condition 2.C.(17)(b)(2) which was incorporated into the License as a
result of Generic Letter No. 81-18 dated March 30, 1981, in which the staff requested all operating BWR licensees to provide diversity for the SDV level switches at their facilities.
The NRC staff finds the proposed changes acceptable with the exception of one change.
This change is on page 3/4 3-8 Table 4.3.1.1-1 "Reactor Protection System Instrumentation Surveillance Requirements."
The licensee has proposed a quarterly surveillance interval for the channel functional test for the SDV float switches.
We find this proposed surveillance interval to be unacceptable for the reasons listed below.
The objective of this design modification is to provide reliable instrumentation which can accommodate a single random failure or potential common-cause failures for all postulated SDV filling events.
It is extremely important that there be sufficient volume in the SDV for accepting a full rea'ctor scram at all times.
Investigations and tests performed by the BWR licensees have shown that crud
- buildup, human error, manufacturing defects, hydrodynamic forces (IE Bulletin 80-14 dated June 12, 1980) and environmental concerns such as those reported with the flooding and heating switches have led to past common-cause failures.
These failure modes would become undetectable for a maximum period of 92 days (quarterly) based on the licensee's proposed surveillance interval instead of 31 days (monthly) based on the original SSES, Unit 1 TS.
In view of the above, the staff concludes it is not appropriate to change the channel functiona'1 test from a monthly to a quarterly surveillance interval, i.e., in a non-conservative direction.
Therefore, the licensee should establish the monthly functional test interval for the float switches or provide adequate justification for the establishment of the quarterly. functional test for Susquehanna, Unit 1.
8504300016 850423 PDR ADOCK 05000387, P
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The staff has determinqd that the remaining technical specification changes are consistent with the staff guidelines as stated in the December 1, 1980 8WR Scram Discharge System Safety Evaluation and in Generic Letter No. 81-18 dated March 30, 1981.
Environmental Consideration This amendment involVes'a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibilitycriteria for categorial exclusion set forth in 10 CFR 51.22(C)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this 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 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:
APR 8 S ~
Docket No. 50-387 APR g 8 II Mr. Norman W. Curtis Yice President Engineering and Construction - Nuclear Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Curtis:
SUBJECT:
AMENDMENT NO.
41 TO FACILITY OPERATING LICENSE NO. NPF SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 The Nuclear Regulatory Commission has issued the enclosed Amendment No. 41 to Facility Operating License" No.
NPF-14 for the Susquehanna Steam Electric Station, Unit 1.'he amendment is in response to your letter dated November 13, 1984.
This amendment reflects the TS changes necessary to support modifi-cations required to comply with License Condition 2.C.(17)(b)(2).
The staff has found one of your requested
- changes, however, to be unacceptable.
Specifically, your proposed quarterly surveillance interval for the channel functional test for the SDV float switches has been denied.
A copy of the related safety evaluation supporting Amendment No.
41 to Facility Operating, License NPF-14 is enclosed.
Sincerely, Grigina1 signed bus
Enclosures:
l.
Amendment No. 4l to NPF-14 2.
Safety Evaluation cc w/
Enclosures:
See next page A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing Distribution:
See next page
- Previous concurrence concurred on by:
- LB¹2/DL/LA
- LB¹2/DL/PM
- OELD KB¹2/DL/BC F AD/L/DL EHylton MCampagnone:lb JGoldberg ASchwencer TMNovak 04/04/85 04/03/85 04/05/85 04/04/85 04/ 12/85 yaO
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