IR 05000313/1994024
| ML20202B974 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/25/1997 |
| From: | Kalman G NRC (Affiliation Not Assigned) |
| To: | Hutchinson ENTERGY OPERATIONS, INC. |
| References | |
| 50-313-94-24, 50-368-94-24, TAC-M92069, NUDOCS 9712030228 | |
| Download: ML20202B974 (4) | |
Text
{{#Wiki_filter:November 25, 1997
SUBJECT:
PRESSUPi2ER SAFETY VALVE OPERABILITY ARKANSAS NUCLEAR ONE, UNIT 1, (TAC NO. M92069)
Dear Mr. Hutchinson:
- NRC Inspection Report 50-313/94-24;50-368/94-24 contains Unresolved Item 313/9424-02. This unresolved item consists of issues related to operability requirements of the Arkansas Nuclear One, Unit 1 (ANO-1) pressurizer safety valves and associated reporting requirements.
As described by the inspection report, both pressurizer safety valves were found out of tclerance during pressure tests in 1993. Valve PSV-1001 was +4.5% out-of-tolerance and valve PSV-1002 was +3.1% out-of-tolerance.
It was . not clear at the time of the inspection what defines operability of the safety valves and whether a Licensee Event Report was required when the valves were found to be out-of-tolerance. As a result, the issue was designated as an unresolved item.
Technical Specification (TS) 2.2.2 defines safety valve operability in terms of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code. The Code requires the nominal pressure setting of at least one safety valve to be no greater than the design pressure of the vessel, additional valves may have higher nominal settings, but in no case greater than 105 percent of the design pressure. Standard TSs include a specific value for safety valve setpoints under the Limiting Condition for Operation (LCO) section. The bases section of the standard TSs propose i 3% of the design pressure as the LCO value. The 1970's vintage ANO-1 Technical Specifications do not define operability in terms of safety valve setpoints, / however the Bases Section of the TSs discuss safety valve requirements in '] terms that are currently used in the standard TSs.
, r gU)) in evaluating this matter it was concluded that the primary system integrity f and plant safety will be assured if either the ASME or the standard TS safety valve operability criteria are used. The dichotomy between the ANO-1 TS and the TS Bases is significant from the standpoint of defining regulatory operability criteria and determining when to initiate Licensee Event Reports.
In-all cases, when safety valves are found out-of-tolerance, they are reset to the same acceptable tolerance (+/- 1% of this design pressure) before the primary system is repressurized.
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>" 1.1lllllI.lll,Il.llI.lll ll . . - - - - - _
___ . . ... .. .. .. . . .. . . ." Mr. C. Randy Hutchison-2-The unresolved item identified by Inspection h urt 50-313/9424; 50-368-24 is an example of a TS flaw that developed over time due to the evolution of the TS format and content since ANO-1 was licensed. The planned conversion to the standard TSs in 1998 will eliminate this TS deficiency at ANO-1.
If your plans to initiate the standard TS conversion process in 1998 change, we recommend that you submit a TS amendment request to clarify safety valve operability requirements.
Pursuant to telephone conversations with Dale James of your staff, it is our understanding th:1 you will take the following actions to resolve this matter: (1) Until standard TS are adopted or a license amendment is issued to address this matter, existing TS operability requirements will be interpreted in terms of the standard TGs, i.e. pressurizer safety valves are operable when their lift settings are within +/- 3% of the design pressure.
(2) Not later than the end of 1998, a conversion to the standard TS will be initiated or a TS amendment will be submitted to clarify the safety valve operability requirements in the existing TSs.
Unresolved Item 313/9424-02 will be closed based on the resolution described above. Notify us immediately if your understanding of the proposed resolution of this matter differs from that set forth above.
Sincerely, ' cD cs % / 40/ George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50,13 cc: See next page _ __ -___ _ _ _ _ - _ - _ ___
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. f
, Mr. C. Randy Hutchison-2- ' . ., .
.
The unresolved item identified by Inspection Report 50-313/9424; 50-368-24 is .'/ an! example of a TS flaw that developed over time due to the evolution of the - a' - TS! format' and content since ANO-1 was licensed. The planned conversion to:thes , - standard TSs-in 1998 will eliminate this TS deficiency at ANO-1.
If your
- ~ , .. - plarn'to, initiate the standard TS conversion process in 1998 change, we.
. . -recommend that you submit a-TS amendment request to clarify safety valve.
,jt ' ., - operability-requirements.
- '
? Pursuant to telephone conversations with Dale James of your staff, it is our . understanding that you will take the following actions to resolve this matter:
. ,(1) Until standard TS are adopted or a license amendment is issued to ' , . ' ' address this r..atter, existing TS operability requirements will be + > interpreted in terms of the standard TSs, i.e. pressurizer safety - , ' valves are operable when their lift settings are within +/ '3% of , the design pressure.
' ' ' (2) Not later than the end of 1998, a conversion to the standard TS will ' be initiated or a TS amendment will be submitted to clarify the ' , safety valve operability requirements in the existing TSs.
- Unresolved Item 313/9424-02 will be closed based on the resolution described above. Notify us immediately if your understanding of the proposed resolution I
of this matter differs from that set forth above.
Sincerely, ORIGINAL SIGNED BY: George Kalman, Senior Project Man.ger Project Directorate IV-1 Division of Reactor Projects Ill/IV , Office of Nuclear Reactor Regulation
Docket No. 50-313 . cc: See next page 01SlRifNILQN: Docket File-PUBLIC PD4 1 r/f JRoc ACRS JClifford EAdensam (EGAl) OGC 6Kahan CHawes TGwynn RIV Document Name: AR92069.LTR
- See previcus concurrence 0FC PM/PD4-1 LA/PD4-1 RIV*
(A)PD/PD4,1) - NAME GKilipan: sp CHawes dr.'s JCliffor[ [ ' DATE d /97 /0 /j//97 7/7/97 h /97 I' U COPY,YES/NO YES/NO YES/NO kNO , 0FFICIAL RECORD COPY " < .
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- ,. . Mr. C. Randy Hutchinson-Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1 CC: Executive Vice President Vice President, Operations Support .& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 Wise,-Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regalatory Commission 611 Ryan Plaza trive, Suite 400 Arlington, TX 75011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 , }}