ML17228A462
| ML17228A462 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/14/1994 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17228A463 | List: |
| References | |
| PROC-940114, NUDOCS 9403070407 | |
| Download: ML17228A462 (48) | |
Text
St. Lucie Unit No.
1 Docket No. 50-335 Second Ten-Year Inservice Ins ection Interval Inservice Testin Pro ram Revision 4
ATTACHMENT 1 Summary of Changes for St. Lucie Unit 1 Inservice Testing Program Revision 4 1 0 Introduction'here are two major changes incorporated in the introduction to the IST program introduction.
The first change was the adoption of new safety / relief valve testing requirements set forth in the ASME / ANSI OM-1987, Part 1.
The second change was the addition of a basic scope document which explained the steps taken to review plant systems for inclusion in the IST program.
1.1 IST Pro ram Testin Re uirement Guidelines'his section has been added to this revision to list the 17 guidelines used for the evaluation of system components (pumps and valves).
2.0 A
licable Documents'tems 2.8 through 2.18 have been added to address the increased number of documents used in the generation of this revision.
~Aeodix A Pum Pro ram Relief Tables:
The Diesel Generator Fuel Oil Transfer pumps have been deleted from the program.
The diesel fuel oil system has been reevaluated and found to fall outside of the required scope of the IST program.
Therefore, appropriate testing of the Diesel Generator Fuel Oil Transfer pumps will continue, but not under the jurisdiction of the ASME IST program.
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~Aeudix B Pum Pro rem Relief Re uests AllPump Relief Requests A section describing the status of approval was added to each relief request.
PR-2 Relief request PR-1 allows the deletion of measuring pump bearing temperatures, therefore, the inclusion of accuracy of portable temperature instruments has been deleted from PR-2.
The accuracy requirements for portable tachometers has remained.
PR-3 This relief request has been deleted by this revision.
The Safety Evaluation Report (SER) dated 26 February 1992 stated that this relief request was not required.
PR-5 Additional information has been included in the Basis for Relief section to improve the explanation for the proposed Alternative Testing.
This alternate testing agrees with the requirements of the NRC Generic Letter 89-04, Position 9 and is considered to be approved upon submittal.
PR-7 This relief request has been deleted by this revision.
The diesel fuel oil system has been reevaluated and found to be outside of the required scope of the IST program.
Appropriate testing of the Diesel Generator Fuel Oil Transfer pumps will continue, but not under the jurisdiction of the ASME IST program.
PR-8 This relief request has been revised to remove reference to the Diesel Generator Fuel Oil Transfer pumps.
The diesel fuel oil system has been reevaluated and found be outside of the required scope of the IST program.
Appropriate testing will continue, but not under the jurisdiction of the ASME IST program.
PR-13 This relief request was originally submitted based upon the initial frequency response of the vibration instrumentation used at St. Lucie. Further investigation with the manufacturer has shown the actual frequency is much lower than originally presented.
The ICW pumps rotate at approximately 885 cpm.
Therefore, the minimum frequency response to comply with the Code is 442.5 cpm.
The instrumentation used has a frequency response down to 270 cpm
(-3dB). Therefore, this relief is no longer required and has been deleted by this revision.
~Aendix C Valve Pro ram Tables:
The changes made to the Valve Program Tables willnot be directly addressed here but are summarized in a marked up copy of the revision 3 tables.
~Aendix D Valve Pro ram Re nests for Relief:
AllValve Relief Requests A section describing the status of approval was added to each relief request.
VR-2 In revision 3 of this relief request, both check valves and motor operated valves were addressed by this relief. In order to avoid any confusion, the MOVs have been removed from this relief request and have been placed in a new relief request VR-39.
Since the basis for relief and alternate testing for the check valves is the same as was approved in VR-2 revision 3, the revision 4 of this relief request is also assumed to be approved.
VR-6 The revision 3 of this relief request was approved provided that St. Lucie develop a method to partial-stroke exercise these valves each cold shutdown.
A partial stroke open test, performed during cold shutdown, has been added to revision 4.
- Also, a subsequent evaluation of the safety functions of check valve V-2191 has shown that its ability to close during emergency boration is not required in order for the system to fulfillits safety function.
Therefore, the closed test for this valve has been deleted from the relief request.
Since the change to this relief request deletes a non-safety related test, the relief request is still considered to be approved by the SER dated 26 January 1992.
VR-9 The revision 3 of this relief request was approved provided that St. Lucie develop a method to partial-stroke exercise these valves each cold shutdown.
A partial stroke open test, performed during cold shutdown, has been added to revision 4.
VR-10 This revision has been updated to include the plant's response to Anomaly P8 addressed by the St. Lucie Unit 1 SER issued by the NRC on 26 February 1992.
As part, of this response, a backflow test has been added to the latest revision of this relief request.
Since the alternate testing agrees with the guidelines of the NRC Generic Letter 89-04 and the SER dated 26 February 1992, this relief request is considered approved.
VR-11 The revision 3 of this relief request was not approved by the SER dated 26 February 1992. In response to the denial of revision 3 of this relief request, an updated relief request was submitted to the NRC. This latest revision of this relief request has been approved by the NRC Safety Evaluation dated 17 September 1993.
VR-22 This relief request has been revised to stipulate that these valves have a safety function to close as well as to open.
This latest revision of this relief request has been approved by the NRC Safety Evaluation dated 17 September 1993.
VR-24 The nitrogen zero gas system has been re-evaluated and was found to not perform any required safety function.
Therefore, these valves have been dropped from the IST program and this relief request deleted.
VR-26 The diesel fuel oil system has been reevaluated and found to be outside of the required scope of the IST program.
Appropriate testing will continue, but not under the jurisdiction of the ASME IST program.
This relief request has been deleted from the IST program.
VR-27 The diesel air start system has been reevaluated and found to be outside of the required scope of the IST program.
Appropriate testing will continue, but not under the jurisdiction of the ASME IST program.
This relief request has been deleted from the IST program.
VR-29 Revision 3 of this relief request stated that these valves will be disassembled and inspected each refueling outage.
This has been changed to a full fiow exercise test to be performed each refueling outage in revision 4.
The flow rate is to be calculated by measuring the level change in the RWT and then dividing the change in volume by the length of the HPSI pump run time.
Testing at each refueling outage is allowed by OM-10. OM-10 specifies that full-stroke exercising at each refueling outage is acceptable iftesting is impractical both quarterly while in operation and during cold shutdown outages.
This relief request is listed for documentation purposes only as required by the Code QWV-3412, IWV-3522, and OM-10, paragraph 6.2), and no approval is required.
VR-30 Revision 3 of this relief request stated that these valves will be disassembled and inspected each refueling outage.
This has been changed to a full flow exercise test to be performed each refueling outage in revision 4.
The flow rate is to be calculated by measuring the level change in the RWT and then dividing the change in volume by the length of the LPSI pump run time.
Testing at each refueling outage is allowed by OM-10. OM-10 specifies that full-stroke exercising at each refueling outage is acceptable iftesting is impractical both quarterly while in operation and during cold shutdown outages.
This relief request is listed for documentation purposes only as required by the Code gWV-3412, IWV-3522, and OM-10, paragraph 6.2), and no approval is required.
VR-32 The testing of these valves has been moved to cold shutdown and therefore does not require a specific relief request.
This relief request has been deleted from the IST program.
VR-35 Interim relief was granted by the NRC SER dated 26 February 1992.
Additional information was submitted to the NRC and this relief request was approved by the SER dated 29 January 1993.
VR-36 The internals for these check valves have been removed.
The safety function performed by these valves has been transferred to other valves in the system.
This relief request has been removed from the IST program.
VR-37 The testing of these valves has been moved to cold shutdown and therefore does not require a specific relief request.
This relief request has been deleted from the IST program.
VR-39 In order to avoid any confusion, the MOVs have been removed from relief request VR-2 and has been placed in this new relief request.
Since the basis for relief and alternate testing for the MOVs is the same as was approved in VR-2 revision 3, the revision 4 of this relief request is also assumed to be approved.
VR-40 Following the removal of the iriternals of check valves, V-08448 and V-08492, check valves V-08130 and V-08163 assumed the safety functions of these valves.
These check valve are to be disassembled and inspected each refueling outage.
This alternate testing agrees with the guidelines of the NRC Generic Letter 89-04, Position 2 and, as such, is considered to be approved upon submittal.
VR-41 Following the removal of the internals of check valves, V-08448 and V-08492, check valves V-08372 and V-08373 were installed in the system and assumed the safety functions of these valves.
These check valve are to be disassembled and inspected each refueling outage.
This alternate testing agrees with the guidelines of the NRC Generic Letter 89-04, Position 2 and, as such, is considered to be approved upon submittal.
~Aendix E Valve Pro ram Cold Shutdown Justifications:
Deleted justifications for performing testing only during cold shutdown for the following valves:
MV-02-2 V-2504 HCV-3618 HCV-3628 HCV-3638 HCV-3648 HCV-08-2A HCV-08-2B V-08448 V-08492 V-09248 V-09280 MV-21-2 MV-21-3 TCV-14-4A TCV-14-4B MV-14-5 thru 8 Valve removed from program - no safety function Now tested quarterly Now tested quarterly Now tested quarterly Now tested quarterly Now tested quarterly Now tested quarterly Now tested quarterly Valve internals removed Valve internals removed Valve inspected per VR-38 Valve inspected per VR-38 Now tested quarterly Now tested quarterly Now tested quarterly Now tested quarterly Valves removed from program - no safety function Added justifications for performing testing only during cold shutdown for the following valves:
PCV-1100E PCV-1100F V-6779 V-27101 Valve added to program - safety function not previously identified Valve added to program - safety function not previously identified Test involves containment entry and breaching containment isolation, test was previously identified to be performed quarterly Valve previously tested each refueling per relief request VR-32 which has been withdrawn
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- 09/01/91 Saint Lucia Nuclear Plant
- Unit 1
PAGE 5
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NORH REH FAlL TEST RELIEF VALVE MWBER COORO.
CL CAT.
SIZE TYPE A/P TYPE POS.
IND HOOE EXAH FREO REO.
REHARKS V.1200
'.1201 V.1202 V.1402 G 6 1
C G.6 1
C G.B 1
B G6 1
C 6%60 SAFETY A
S/A C
NO S, OP0
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S/A C
NO 3P 6$080 SAFETY A
S/A C
NO D.yyO 2.500 GLOBE A
SO C
YES FC SRV RF SRV RF EO PI CS 2Y SRV RF V.1403 G.8 1
8 2.500 GATE A
HO 0
YES FAI EC QR Pl 2Y V.1404 H.S 1
8 2.500 GLOBE A
SO C
YES FC EO CS Pl 2Y V.1405 K-8 1
8 2.500 GATE A
HO 0
YES FAI EC QR Pl 2Y V-1441 0.4 2
B 1.000 GLOBE A
SO LC YES FC EO CS Pl 2Y V-1442 0-4 2
B 1.000 GLOBE A
SO LC YES FC EO CS Pl 2Y V-1443 N-6 2
B 1.000 GLOBE A
SO LC YES FC EO CS Pl 2Y V-1444 N-6 2
B 1.000 GLOBE A
SO LC YES FC EO CS Pl 2Y V.1445 F.S 2
B F 000 GLOBE A
SO LC YES FC EO CS Pl 2Y V-1446 F.8 2
8 1.000 GLOBE A
SO LC YES FC EO CS PI 2Y V.1449 F.S 2
B 1.000 GLOBE A
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- 09/01/91 Saint Lucie Nuclear Plant. Unit 1
PAGE 15
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CL CAT.
SIZE TYPE A/P TYPE POS.
IND HODE EXAH TEST RELIEF FRED RED.
REHARKS V.3247 B
1 1
AC 12.MO CNECK A
S/A C
NO CV/C ~
VR.13 CV/PO CS VR 13 INSP RF VR-13 SLT 2 2Y VR-2 V.3468 0 7 2
C 2.000 RELIEF A
S/A C
NO SRV RF V.3469 E 4 P C
1.000 RELIEF A
S/A C
KO SRV RF V-3480 E-5 1
A 10.000 GATE A
SLT-2 CS 2Y 2V Va-a V t'.-3~
V.3481 E-5 1
A 10.000 GATE A
HO LC YES FAI EO Pl SLT.2 CS 2Y 2Y VI42 V-3482 E5 WC I
1.000 RELIEF A
S/A C
NO SRV RF V-3483 E-6 2
C 2.000 RELIEF A
S/A C
NO SRV RF V-3614 F.5 I IL. 8 12.000 GATE A
HO LO YES FAI EC Pl CS 2Y V-3624 F 2 Q
8 12.MO GATE A
HO LO YES FAI EC Pl CS 2Y V-3634 V-3644 8-5
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HO LO YES FAI EC Pl CS 2Y CS 2Y V-3651 D 4 1
A 10.000 GATE A
HO LC YES FAI EO Pl SLT-2 CS 2Y 2Y ~ YZ-$ t V-3652 V-3(tI u-3'
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- 09/01/91 Saint Lucia Nuclear Plant - Unit 1
PAGE t
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NORII REN FAlL TEST RELIEF VALVE NWBER COORD.
CL CAT.
SIZE TYPE A/P TYPE POS.
IND KOE EXAN FREQ REQ.
REHARKS FSE-27 8 C-11 2
A 0.375 GLOBE A
SO C
YES FC EC EO FS PI SLT-1 QR QR QR 2Y 2Y FSE-27 9 C.14 2
A 0.375 GLOBE A
SO C
YES FC EC QR EO QR FS QR Pl 2Y SLT-1 2Y V-27101 8-13 2
AC 0.375 CHECK A
S/A C
NO CV/C CV/0 QR SLT-1 2Y V-27102 8.13 2
AC 0.375 CHECK A
S/A C
NO CV/C C5'Rf CV/0 QR SLT-1 2Y V.27105 E-13 2
C 0.375 CHECK A
S/A C
NO CV/0 QR V-27110 E 13 2
C 0.375 CHECK A
S/A C
NO CV/0 QR
V.P l
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