PLA-1430, Application for Amend 15 to License NPF-14,consisting of Proposed Changes to Tech Specs Re Administrative Controls, Special Test Exemption for Oxygen Concentration,Leakage in RCS & Refueling Operations
| ML17139B233 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/10/1982 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17139B234 | List: |
| References | |
| PLA-1430, NUDOCS 8212170271 | |
| Download: ML17139B233 (7) | |
Text
REGULATORY'
~RMATION DISTRIBUTION SYST~ (RIDS)
ACCES'SION" NBR 8212170271 DOC ~ DATE: 82/12/10 NOTARIZED:
NO
'OCKET ¹ FACIL:50 387 Susquehanna Steam Electric Stationr Unit 1< Pennsylva 05000387 AUTH BYNAME AUTHOR AFFILIATION CURTIS@ N ~ l'le Pennsylvania Power L Light Co.
REC IP ~ NAME RECIPIENT AFFILIATION SCHNENCERgA, Licensing Branch 2
SUBJECT:
Application for Amend 15 to License NPF-'14<consisting of proposed changes to Tech Specs re administrative controlsr special test exemption for oxygen concentration<leakage in RCS 8 refueling operations, DISTRIBUTION CODE:
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Pennsylvania Power 8 Light Company Two North Ninth Street
~ Allentown, PA 18101
~ 215/ 770.5151 Norman W. Curtis Vice President-Engineering 8 Construction-Nuclear 21 5 / 770-5381 DEC 10 1982 Mr. A. Schwencer, Chief Licensing Branch No.
2 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT 15 TO LICENSE NPF-14 ER 100450 FILE 841-8 PLA-1430 Docket No. 50-387
Dear Mr. Schwencer:
The purpose of this letter is to present several proposed changes to Appendix "A" to License No. NPF-14, the Susquehanna SES Unit 1 Technical Specifications.
ITEM 1:
Specification 6.5.2.8.e.
Proposed Change:
Revise per Attachment 1
Justification for Change:
Generic Letter No. 82-17 ITEM 2:
Specification 6.5.2.8.f.
Proposed Change:
Revise per Attachment 2
Justification for Change:
Generic Letter 82-23 ITEM 3:
Epecificacica 6.'9.1.6 g~c3l
~//ATE
'roposed Change:
Revise per Attachment 3
Justification for Change:
During the reorganization of the NRC, the Management Information Branch became the correct addressee for Monthly Operating Reports.
ITEM 4:. Specification 3.10.5 Proposed Change:
Revise per Attachment 4A
(~821217027l 82i2i0 PDR ADOCK 05000387 P
1
DPC 10 198K Page 2
SSES PLA-1430 ER 100450 File 841-8 Mr. A. Schwencer, Chief Justification for Change:
Special Test Exception 3.10.5 was written in order to provide access to primary containment during startup testing.
The Susquehanna SES Startup Test Program is, currently projected to be complete in late March or early" April, 1983.
1, I
10CFR50.44 (Attachment 4B) requires SSES to have an inerted atmosphere 6 months after initial criticality March 10, 1983.
An exemption is requested in order to allow SSES to finish startup te'sting before having to inert primary containment, based on the belief that there is no safety impact associated with the 6~onth restriction as long as SSES is held to Specification 3.10.5.'TEM 5:
Specification 3.4.3.2 Proposed Change:
Revise per Attachments 5A and 5B Justification for Change:
This change is consistent with the commitments made in PPSL's response (dated November 2, 1982) to the sua sponte question raised by theAtomic Safety and Licensing Appeal Board, (Order dated October 26, 1982).
ITEM 6:
Specification 3.9.1 Proposed Change:
Revise per Attachment 6
Justification for Change:
The proposed change clarifies the intent of the "NP" footnote.
The LCO requires the mode switch to be locked in the Shutdown or Refuel position.
The footnote permits movement to alternative positions when testing of switch functions is being performed.
Moving the footnote to the Applicability statement enhances operator awareness of this provision.
ITEM 7:
Specification 4.8.4.1.a.2.
Proposed Change:
Revise per Attachment 7
Justification for Change:
The existing requirement requires sample testing (10% minimum) of the protective fuses for primary containment penetration circuits on a rotational basis.
The purpose of this requirement is to assure circuit isolation on fault conditions to prevent heating of the penetration seal and possible subsequent damage.
This mode of protection requires that the fuse open when currents in excess of the fuse rating occur, Also of concern is the assurance that the fuse will not prematurely open thereby isolating a circuit unnecessarily.
The existing sample test described in Specification 4.8.4.1.a.2 is a resistance measurement of the fuse against the manufacturer's design resistance.
Manufacturers,
- however, from time-to-time change fusable materials or make other design changes which will change the design resistance tolerance.
These changes are not announced to the users and are generally not distinguishable by unique part numbers or other physical changes since the fuse protective rating is not changed.
Resistance values measured during the test could then lead one to an erroneous conclusion regarding the fuse's condition.
DFC 10 l982 Page 3
SSES PLA-1430 ER 100450 File 841-8 Mr. A. Schwencer, Chief The proposed change described herein is to replace all primary containment protection fuses periodically with new fuses.
The replacement fuses are resistance tested and certified by the manufacturer.
This change will reduce maintenance time to perform the work and reduce fuse premature opening caused by component aging.
Since all fuses used in primary containment penetration protective circuits will be periodically replaced with fuses tested to the proper resistance instead of a sample testing of fuses to an uncertain resistance value, plant safety will be increased by this change.
ITEM 8:
Specification 4.6.1.7 Proposed Change:
Revise per Attachment 8
Justification for Change:
The purpose of the proposed change is to update the Specification to the design drawings.
These changes have no impact on the safe operation of SSES; they merely reflect the actual configuration of the plant.
We have determined this proposed amendment to be Class IV in nature and have enclosed the appropriate fees pursuant to 10CFR170.
Very truly yours, N.
W. Curtis Vice President-Engineering 6 Construction-Nuclear Attachments cc:
R. L. Perch USNRC
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