ML17158B962
| ML17158B962 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/25/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17158B961 | List: |
| References | |
| NUDOCS 9703030443 | |
| Download: ML17158B962 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETYNEVALUATION BY THE OFFICE OF NUCLEAR REACTO REGULATION EL TED TO M NDMENT NO.
TO ACILITY OPERA ING LICENSE NO.
F-14 AMENDMENT N0.1 34 0 FACILITY OPERATING LICENSE NO.
PF-22 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
SUS UEHANNA STEAM ELECTRIC STATION UNITS 1
AND 2 DOCKET NOS.
50-387 AND 388 l.
~INTN I N
By letter dated February 2,
- 1996, as supplemented September 23,
- 1996, Pennsylvania Power and Light Company (the licensee) submitted a request for changes to the Susquehanna Steam Electric Station (SSES),
Units 1 and 2, Technical Specifications (TSs).
The requested changes would change TS 3.6. 1.2c for each unit to permit main steam isolation valve (HSIV) local leak rate tests (LLRTs) to be performed with a test pressure of either 22.5 or 45.0 psig depending on the system configuration at the time of testing.
The September 23, 1996, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination or change the amendment request as originally noticed.
Part 50, Appendix J, Option B,Section III.B, "Type B and C tests," of 10 CFR states:
"The tests must demonstrate that the sum of the leakage rates at accident pressure of Type B tests, and...Type C tests, is less than the performance criterion (La) with margin, as specified in the Technical Specifications."
"Accident pressure" or Pa, for SSES is 45.0 psig.
- However, the SSES TSs currently specify that the HSIVs be tested with a test pressure of 22.5 psig.
The MSIV leakage acceptance criteria would not be changed with this amendment.
2.0 DISCUSSION AND EVALUATION Two MSIVs are provided in each main steam line (HSL) of SSES, Units 1 and 2,-
installed in such a manner that normal steam flow tends to seat the valve disks.
Test connections are installed upstream of each HSIV, however the upstream test connection cannot be used because the HSL is open to the reactor vessel.
This arrangement, which is necessary for steam system functional
- reasons, renders it impractical to test the MSIVs in the forward direction at full accident pressure since the test pressure tends to unseat the inboard HSIV.
As indicated in the Standard Technical Specifications, the staff therefore authorizes exemptions to permit MSIVs to be leak rate tested at 9703030443 970225 PDR ADOCK 05000387 PDR
a reduced pressure of 22.5 psig.
Since this test method does not involve putting full test pressure on either MSIV disk in the close direction the test results are considered conservative.
Testing at the reduced pressure of 22.5 psig had been approved by the staff and was included in the current TSs.
However, there is one occasional plant condition during which it is practicable to perform MSIV leak rate tests in accordance with Appendix J.
When plugs are installed in the MSL nozzles in the reactor
- vessel, with suitable restraining devices, a closed cavity is formed between the reactor vessel and upstream MSIV enabling test pressure to be applied to each MSIV (with the other MSIV open) in the accident direction.
It then becomes practicable to test in full accordance with Appendix J and this was the proposed TS addition that the staff has evaluated.
Since the results of this test method are more accurate, this test method is acceptable and may be used when the MSL plugs are installed.
The staff has also determined that the proposed amendment, which only deals with the measurement of leakage from the main steam line, would not adversely affect the basis for the August 15,
- 1995, Appendix J, exemption which increased the allowable leakage rate for MSIVs for the Susquehanna units.
Based on the above, the staff finds that the proposed alternate test method is consistent with Appendix J testing requirements and is acceptable.
3.0 STATE CO SULTATION In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendments involve 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 the amendments involve no significant hazards consideration, and there has been no public comment on such finding (61 FR 42282).
Accordingly, the amendments meet eligibility criteria for categorical 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 the amendments.
- 5. 0 CONCLUSION
'he Commission has concluded, based on the considerations discussed
- above, that:
(I) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
M. Long Date:
February 25, 1997
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