3F0287-11, Application for Amend to License DPR-72,consisting of Change Request 148,revising Tech Specs Re Containment Airlock Surveillance
| ML20211C157 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/17/1987 |
| From: | Eric Simpson FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211C162 | List: |
| References | |
| 3F0287-11, 3F287-11, NUDOCS 8702200024 | |
| Download: ML20211C157 (4) | |
Text
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e' Florida Power COR PO R ATIO N February 17, 1987 3F0287-11 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
SUBJECT:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No.148, Revision 0 Containment Air Locks
Dear Sir:
Florida Power Corporation (FPC) hereby submits Technical Specificat'on Change No.148, Revision 0 requesting amendment to Appendix A of Operating License No. DPR-72. As part of this request, the proposed replacement page for Appendix A is enclosed.
On December 9,1986, NRC granted an exemption to FPC from the requirements of 10CFR50, paragraph III D.2(b)(ii) of Appendix J.
This subnittal updates technical specifications to reflect the exemption.
The exemption revised the requi rements for conducting a full pressure airlock leakage test.
FPC will rely on seal leakage testing as described in paragraph III.D.2(b)(iii) when the reactor is in COLD SHUTDOWN (Mode 5) or REFUELING (Mode 6) and when no maintenance has been performed that affects airlock sealing capabilities. A full pressure airlock leakage test will be performed at least once per six months and following any maintenance that could affect airlock sealing capability.
This testing will verify the sealing capability of the airlock has not degraded as a result of routine use or maintenance since the previous test.
It will also verify the overall airlock leakage rate is wi thin the technical specification limits.
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GENERAL OFFICE: 3201 Thirty fourth Street South
F February 17, 1987 3F0287-11 Page 2 An application fee, check number _ 874578, of one hundred fifty dollars
($150) was previously submitted on December 1,
1986 (3F1286-04) and, therefore, not included with this submittal.
-Sincerely, E. C. Simpson Director, Nuclear Operations Engineering and Licensing JLB:jk Attachment cc: Dr. J. Nelson Grace Regional Administrator, Region II
-Mr. T. F. Stetka Senior Resident Inspector Chai rman, Board of County Commissioners Administrator Radiological Health Services T+-
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 REQUEST NO. 148, REVISION 0 CONTAIMENT SYSTEMS /CONTAIMENT AIR LOCKS LICENSE DOClMENT INVOLVED: TECHNICAL SPECIFICATIONS PORTIONS: Surveillance 4.6.1.3.
DESCRIPTION OF REQUEST:
This submittal requests an update to the containment air lock surveillance to re-flect the exemption issued to Crystal River Unit 3 regarding the requirements of 10CFR50 Appendix J, III.D.2(b)(ii).This exemption allows substitution of an air lock seal test for an air lock pressure test while the reactor is in a shutdown or refueling mode.
The surveillance requirement to conduct a full pressure air lock leakage test whenever air locks are opened during periods when containment integrity is not required, will be changed such that the test need only be performed at least once per six months and following any maintenance that could affect air lock sealing capability.
This submittal also requests the deletion to a
footnote
(*)
in technical specification 4.6.1.3.a regarding exemption to Appendix J of 10CFR50.
The requirement is no longer applicable to the latest revision of Appendix J, and therefore, no exemption is necessary.
REASON FOR REQUEST:
The Commission has issued an exemption to Crystal River Unit 3 regarding containment airlock surveillance requirements described in Appendix J, III.D.2(b)(ii) of 10CFR Part 50. This exemption allows substitution of an air lock seal test for an air lock pressure test while the reactor is in a shutdown or refueling mode.
The full pressure (Pa) test wi11 continue to be performed at least once every six months, however, prior to ascending to Mode 4 this test would only be conducted if maintenance activities were performed which could have affected air lock sealing capabili ty.
FPC will perform an air lock seal test by pressurizing the air lock door gasket interspaces to 8 psig if the doors had been opened.
If the doors had not been opened, the six month full pressure (49.6 psig) test would demonstrate the overall sealing capabilities.
Opening of the air lock has the potential of altering the sealing capability of the air lock because of possible damage to the seals.
The door operator (hand wheel) shaf t seals experience very little alteration as the shaf ts rotate within packing.
History indicates the shaft seals are effective in maintaining the sealing capability, even with door operation, and a full pressure test every six months and af ter maintenance is sufficient to assure operability.
Contrary to the shaft seals, the door seals could experience alteration when the doors cycl e.
The alterations occur as the knife edges impact the seals.
Pressurization of the volume between the seals to 8 psig after each opening, and prior to establishing containment integrity, provides the necessary surveillance to ensure the sealing capability of the door seal s.
Addi tionally, the sealing capability of the doors is ensured by the performance of a full pressure test af ter maintenance which could affect air lock door gasket sealing capability.
This change conforms to the latest revision of the Standard Technical Specifications (NUREG 0452) and is consistent with the exemption issued to Crystal River Unit 3 regarding the requirements of 10 CFR 50, Appendix J, III.D.2(b)(ii).
SAFETY EVALUATION:
Previous air lock leakage test resul ts have been wi thin limits as specified by Technical Specifications.
To assure air lock leakage continues to be within specified limits, an air lock leakage test at full pressure (49.6) will be performed prior to establishing primary containment integri ty when maintenance has been performed on the air lock that could affect its sealing capability.
Additionally, an air lock seal test will be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closure, except when the air lock is being used for multiple entries and then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Testing as described above will measure the leakage through the door operator shaf t seals and provide assurance that the air lock will not leak excessively and will not affect containment integrity or increase the risk of facility accidents.
,SHOLLY EVALUATION:
Florida Power Corporation (FPC) proposes this amendment does not involve a signifi-cant hazards consideration.
This change conforms to the latest revision of the Standard Technical Specification (NUREG 0452). Substituting an air lock seal test for an air lock pressure test while the reactor is in a shutdown or refueling mode has no significant impact upon plant operation or safety.
Tests as described in the Technical Specifications will continue to demonstrate containment integrity.
Previous air lock leakage test results have been wi thin limits as specified by technical specifications.
Based on the history of the containment air locks and previous test results, it is unlikely that significant leakage would occur.
Based on the above, FPC finds the amendment will not:
1)
Involve a significant increase in the probability or consequerce of an accident previously evaluated because previous test results were satisfactory and significant leakage is not expected.
2)
Create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change introduces no new mode of plant operation nor does it require a physical modification.
3)
Involve a significant reduction in the margin of safety.
Any reduction in the margin of safety will be insignificant since air lock seal tests and air lock full pressure leakage tests will provide assurance that the air lock will not leak excessively and will not affect containment integrity.