W3P84-0601, Advises That Listed Procedures & Tech Specs Reviewed,Per Generic Ltr 83-28 Re post-maint Testing of Reactor Trip Sys Components.Check of Vendor & Engineering Recommendations Concluded Test Guidance Incorporated Into Procedures
| ML20081C189 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/05/1984 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2JRRY, GL-83-28, W3P84-0601, W3P84-601, NUDOCS 8403120169 | |
| Download: ML20081C189 (6) | |
Text
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I OUISIANA P O W E R & L i G H T! P O. BOX 6008
- NEW ORLEANS. LOUISlANA 70174 242 O uAnONOe s m er
. (504) 3ti6 2345 Eu?$2vsM March 5, 1984 W3P84-0601 3-A1.01.04 Q-3-A20.02.02 L.02 6
Director of Nuclear Reactor Regulation Attention:
Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Waterf6rd SES Unit 3 Docket No. 50-382 Response to Generic Letter 83-28, Item 3.1 Post Maintenance Testing (Reactor Trip System Components)
Dear Sir:
The subject Generic Letter, in item 3.1, required a review of procedures, vendor recommendations and Technical Specifications applicable to post-maintenance testing of reactor trip system components.
In particular:
3.1.1 Requirement Licensees and applicants shall submit the results of their review of test and maintenance procedures and Technical Specifications to assure that post-maintenance operability testing of safety-related components in the reactor trip system is required to be conducted and that the testing demon-strates that the equipment is capable of performing its safety functions before being returned to service.
Response
LP&L has conducted a review of the procedures listed in and have concluded that, in all cases, the procedures require testing that will adequately assure operability of safety related components before they are returned to service.
3.1.2 Requirement Licensees and applicants shall submit the results of their check of vendor and engineering recommendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or the Technical Specifications, gg where required.
8403120169 840305 PDR ADOCK 05000382 A
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'Page 2' W3P84-0601 3-A1. 01. 04 Q-3-A20.02.02
' Response LP&L has conducted a check of vendor and engineering recom-mendations and has concluded that recommended test guidance is incorporated into the procedures listed in Attachment 1.
3.1.3 Requirement Licensees and applicants shall identify, if applicable, any
. post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than_ enhance safety. Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval.
(Note that action 4.5 discusses on-line system functional testing.)
Response
LP&L has conducted a review of the Technical Specifications
' listed in Attachment 2 and has concluded that none degrade rather than enhance safety.
During our review we have confirmed that the items listed in Attachments 1 and 2 are the only items related to maintanance of reactor trip system components.
Should you have any questions or comments on this matter please contact
- Mike Meisner at' (504) 363-8938.
-Yours very truly, K. W. Cook Nuclear' Support & Licensing Manager KWC/MJM/ch Attachments cc:
W.M. Stevenson,- E.L. Biche, J. Wilson, G.L. Constable
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ATTACHMENT I 1.
ME-4-155 Reactor Trip Switchgear Breakers 2.
MI-3-101 NI Linear Power Channel Calibration Safety Channel A, B, C &.D
.3.
MI-3-102 NI Log Power Channel Calibration Safety Channel A B, C & L 4.
-MI-3-120 Control Element Assembly Position Indicator Isolation Verification Test 5.
MI-3-121 Control Element Assembly Calculator Channel Functional Test 6.
MI-3-122 Control Element Assembly Calculator Channel Calibration 7.
MI-3-125 Core Portection Calculat.or Calibration 4
8.
MI-3-126 Core Protection Calculator Functional Test 9.
MI-3-127 Control Element Assembly Calculator to Core Protection Calculator Optical Isolater Verification Test 10.
MI-3-129 Core Protection Calcularor Refueling Functional Test
-11.
MI-3-130 CEAC Refueling Functional Test 12.
MI-3-201 Plant Protection System Calibration 13.- MI-3-207 Reactor Protection System Response Time Test 14.
MI-3-209 Resistance Temperature Detector Loop Current Step Response Time Test 15.
MI-3-210 High Pressurizer Pressure Sensor Response Time Test l
l 16.
MI-3-211 Low Pressurizer Pressure Sensor Response Time Test 17.
MI-3-212 Steam Generator No. 1 Low Pressure Sensor Response Time Test 18.
MI-3-213 Steam Generator No. 2 Low Pressure Sensor Response Time Test 19.
MI-3-214 Steam Generator No. 1 Low Level Sensor Response
'~
Time Test
-20.
.MI-3-215 Steam Generator No. 2 Low Level Sensor Response Time Test l:
21.
MI-3-216 Containment Pressure (Narrow Range) Sensor Response Time Test 22.
MI-3-219 Steam Generator Differential Pressure (Sheared Shaft)
Sensor Response Time Test
- 23. MI-3-301 Pressuriser Pressure Hi Loop Check and Calibration
- 24. MI-3-302 Containment Pressure (Narrow Range) Loop Check and Channel Calibration
- 25. MI-3-303 Steam Generator No. 1 Pressure Loop Check and Calibration
- 26. MI-3-304 Steam Generator No. 2 Pressure Loop Check and Calibration 27.'
MI-3-305 Steam Generator No. 1 Level Loop Check and Calibration
- 28. MI-3-306 Steam Generator No. 2 Level Loop Check and Calibration 29.
MI-3-307 Reactor Coolant System Hot Lag No.1 Temperature Loop Check and Calibration
- 30. MI-3-308 Reactor Coolant System Hot Lag No. 2 Temperature Loop Check and Calibration
- 31. MI-3-309 Reactor Coolant System Cold Lag No.1 Temperature Loop Check and Calibration
- 32. MI-3-310 Reactor Coolant System Cold Leg No. 2 Temperature Loop Check and Calibration
- 33. MI-3-311 Reactor Coolant Pump 1A Speed Sensor Calibration
- 34. HI-3-312 Reactor Coolant Pump 15 Speed Sensor Calibration
- 35. MI-3-313 Reactor Coolant Pump 2A Speed Sensor Calibration
- 36. MI-3-314 Reactor Coolant Pump 2B Speed Sensor Calibration
- 37. MI-3-315 Containment Pressure (Wide Range) Loop Check and l
Channel Calibration
- 38. MI-3-316 Pressurizar Pressure (Wide Range) Loop Check and Calibration 39.
MI-3-510 Steam Generator No. 1 Differential Pressure (Sheared l
Shaft) Loop Check and Channel Calibration l-40.
MI-3-512 Steam Generator No. 2 Differential Pressure (Sheared Shaft) Loop Check and Channel Calibration e
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41.
MI-4-314 CEDM Reed Switch Bench Check 42.
MI-5-473 CEDM Control System Calibration 43.
MI-13-522 Plant Protection System Ground Detection Test 44.
MI-13-523 Control Element Assembly and Incore Nuclear Instrumentation Repatch Verification
- 45. MM-8-Oll Missile Shield Maintenance Refveling Structure and CEDM Cooling Ducts Installation
- 46. MM-8-023 Reactor 7essel Head Installation 47.
)ti-8-034 Missile Shield Maintenance Refueling Structure and CEDM Cooling Ducts Removal 48.
MM-8-040 Installation and Coupling of CEA Extension Shaft 49.
MM-8-041 CEDM Removal
- 50. MM-8-042 CEDM Installation
- 51. MM-8-043 CEDM Venting and Ball Replacement
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ATTACHMENT 2 4.3.1.1 (2) 4.3.2.2 4.7.10.4.C2 4.3.1.1 (3) 4.7.10.5A 4.3.2.3 4.3.1.1 (4) 4.7.10.5.B1 4.3.3.5 (1) 4.3.1.1 (5) 4.7.10.5.B2 4.3.3.5 (5) 4.3.1.1 (6) 4.7.11.1 4.3.3.5 (7) 4.3.1.1 (7) 4.7.11.2 4.3.3.5 (8) 4.3.1.1 (8) 4.8.1.1.2.D1 4.3.1.1 (9) 4.3.3.6 (2) 4.8.1.1.2.F1 4.3.1.1 (10) 4.3.3.6 (3) 4.3.1.1 (11) 4.3.3.6 (7) 4.8.2.1 4.3.1.1 (13) 4.3.3.8.1 4.8.2.2 4.3.1.1 (14) 4.3.3.8.2 4.8.4.1 4.3.1.1 (15) 4.3.3.8.3 4.3.1.1 (16) 4.8.4.2 4.3.3.8.4 4.3.1.3 4.9.7.2 4.4.2.1 4.3.1.4A 4.3.1.4B 4.4.2.2 4.4.8.1.2 4.3.1.6 4.6.4.2 4.3.2.1 (1B) 4.7.1.1 l
4.3.2.1 (1C)
.4.3.2.1 (2B) 4.7.10.1.2C 4.3.2.1 (3C) 4.7.10.1.3
-4.3.2.1 (3D) 4.7.10.2.C2 4.3.2.1 (4B).
4.7.10.2.C3 4.3.2.1-(4C) 4.7.10.3 4.3.2.1 (53) 4.7.10.3B 4.3.2.1 (7B) 4.7.10.4B1
. 3.2.1 (7C) 4 4.7.10.4B2 4.3.2.1'(8) 4.7.10.4B3 4.3.2.1 (11)
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