ML20137D818
| ML20137D818 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/14/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136C539 | List:
|
| References | |
| FOIA-96-485 NUDOCS 9703260319 | |
| Download: ML20137D818 (2) | |
Text
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ATTACHMENT i
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR R[9ULATION RELATED TO THE INSERVICE TESTING OF MAIN SIEAM SAFETY VALVES FLORIDA POER & LIGHT CO.
ji ST. LUCIE PLANT. UNIT 2 j
DOCKET NUMBER 50-389 f
1.0 INTRODUCTION
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The Code of Federal Regulations,10 CFR 50.55a, requires that inservice 1
testing (IST) of certain American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Cade (the Code) Class 1, 2, and 3 pumps and valves
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be performed in accordance with Section XI of the ASME Boiler and Pressure j
I Vessel Code (the Code) and applicable addenda, except where alternatives have
- j been authorized or relief has been requested by the licensee and granted by the Commission based on impracticalities and limitations of design, materials, or construction. The inservice testing requirements were added to 10 CFR i4 50.55a by rulemaking published in the Federal Reaister february 1976. At the l'
time the inservice testing requirements were originally included, the latest edition of the ASME Code referenced in the regulation was the 1971 Edition, i
with addenda through the Summer 1973 Addenda. Subsequently, the Winter
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Addenda 1973 was~added to the regulations in March 1976. The 1974 Edition
'i with addenda through the Sumner 1975 Addenda _was added to the regulations in January 1977. Later editions and addenda have been incorporated by reference into 10 CFR 50.55a, with the most recent reference being the 1989 Edition which was incorporated by rulemaking effective September 8, 1992.
2.0 DISCUSSION 4
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' Florida Power & Light Company's letter dated May 5,1994, submitted changes to the St. Lucie Plant, Unit 2, technical specifications. The proposed changes would modify the surveillance requirements specified for the main steam safety valves to be consistent with 10 CFR 50.55a requirements for inservice testing.
.i Specifically, the changes propose the deletion of the reference to demonstration of operability of the valves in accordance with the 1974 Edition of the ASME Code. The changes are administrative.
3.0 EVALUATION The St. Lucie' Plant, Unit 2, received a construction permit May 2, 1977. The requirements in 10 CFR 50.55a were that during the initial 20-month interval (now 120-month interval), the inservice testing of pumps and valves for assessing operational readiness comply with those requirements in editions of
)
a j
the code and addenda in effect no more than six months prior to the start of facility commercial operation. Commercial operation for St. Lucie Plant, Unit j
'2, commenced August 8, 1983. Note that the regulations were later changed i
such that the code edition for the initial 120-month interval was to comply i
with the code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the date of issuance of the operating license. The operating license for the St. Lucie Plant, Unit 2, was issued June 10, 1983.
In subsequent intervals, l
the regulations require that the inservice testing program be updated to the i
latest code and addenda incorporated by reference in Paragraph (b) of 10 CFR i
j 50.55a 12 months prior to the start of the interval. The second 120-month interval for the St. Lucie Plant, Unit 2, began August 8,1993. The l
9703260319 970301 7
..' l requirements of the 1986 Edition of Section XI of the ASME Code are implemented by the current inservice testing program at the plant.
The technical specifications for the St. Lucie Plant, Unit 2, were issued with reference to the 1974 Edition of the ASME Code in the surveillance requirements of Specification 4.7.1.1 for the main steam safety valves.
Specification 4.0.5 provides the requirements for implementation of the inservice inspection and testing requirements for the St. Lucie Plant, Unit 2, which indicate that the inspection and testing are to be performed in accordance with Section XI of the ASME Code as required by 10 CFR 50.55a.
As noted above, the current edition of Section XI of the ASME Code for implementation of the inservice testing requirements for the St. Lucie Plant, Unit 2, is the 1986 Edition.
By deleting the reference to the 1974 Edition of the ASME Code, the technical specifications will no longer be inconsistent internally or with the regulations.
No safety concerns are created because the main steam safety valves will continue to be testing in accordance with the requirements of the ASME Code pursuant to Specification 4.0.5.
No changes to the lift settings are proposed i
as part of this change. Therefore, it is acceptable to delete the following sentence in Spec,1fication 4.7.1.1:
t Each main steam line code safety valve shall be demonstrated operaole, with lift settings and orifice sizes as shown in Table 4.7-0, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition.
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Table 4.7-0, which lists the safety valve settings, will be renumbered to
" Table 3.7-2," which changes the character of the table from a " surveillance" requirement to a " limiting condition for operation." Such a change in the character of the table is conservative, as it establishes a condition that more specifically applies at any time the plant is in modes 1, 2, and 3, and not just during testing. Specification 3.7.1.1 will be revised to include a reference to Table 3.7-2, so that it will now state:
"All main steam line code safety valves sha11 be operab1e with lift settings and orifice sizes as shown in Table 3.7-2.
The sentence that will replace the deletion in Specification 4.7.1.1 will state:
No additional Surveillance Requirements other than those required by Specification 4.0.5.
1 The only other change is the table number in the " List of Tables" in the technical specifications ir.dex.
4.0 CONCLUSION
The proposed changes are acceptable for achieving consistency in the surveillance requirements specified for the main steam safety valves and ensuring that the testing of the lift settings are subject to the updated inservice testing requirements for the current and later inservice test intervals.
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