ML20249C202
| ML20249C202 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/23/1998 |
| From: | Gardner R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9806260184 | |
| Download: ML20249C202 (3) | |
Text
i June 23, 1998 1
L Mr. R A. Patulski Site Vice President Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
ANNOUNCEMENT OF GENERIC LETTER NO. 96-01 INSPECTION
Dear Mr. Patulski:
This is to inform you that the NRC will perform an inspection of your implementation of Generic Letter 96-01, " Testing of Safety Related Logic Circuits," at the Point Beach Nuclear Plant, Units 1 and 2. We have chosen the reactor protection system, emergency diesel generator (EDG) loading, EDG load shedding and load sequencing circuits for this review. The inspection will independently assess that all portions of logic circuits are adequately covered in surveillance procedures and that the testing verifies proper EDG loading. The inspection's onsite activities are scheduled for the weeks of July 20 - 23 (pre-inspection), and July 27 - 31,1998 (inspection week). The pre-inspection week will have only regional personnel on-site to prepare for the arrival of NRR personnel from the instrumentation and Controls Branch during the inspection week.
This inspection will assess the adequacy of licensee programs, procedures, training, and supporting documentation to assure that licensee Technical Specification required surveillance testing of safety related logic circuits are being performed.
In order to more effectively perform this task, we would like to have the enclosed preliminary information made available during the week of July 20,1998. Following the entrance on July 27,1998, the team would appreciate a short systems overview presentation followed by a general plar t tour of the control room, reactor protection system and EDG areas, if you have any questions regarding the requested information or on the inspection itself, please contact David S. Butler at (630) 829-9720.
Sincerely, Original /s/ R. N. Gardner Ronald N. Gardner, Chief Engirnering Specialists Branch 2
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Docket Nos.:oSQ-366;6p-301 License Nos~ dPit'2'4; DPR-27
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Enclosure:
As stated See Attached Distribution DOCUMENT NAME: G:DRS\\ pol 06228.DRS v -...
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cc w/ encl:
R. Grigg, President and Chief Operating Officer, WEPCO M. Sellman, Chief Nuclear Officer M. Reddeman, Plant Manager J. O'Neill, Jr., Shaw, Pittman, Potts & Trowbridge K. Duveneck, Town Chairman Town of Two Creeks B. Burks, P.E., Director Bureau of Field Operations Chairman, Wisconsin Public Service Comrnission S. Jenkins, Electric Division Wisconsin Public Service Commission State Liaison Officer
' Distribution:
CAC (E-Mail)
J. Wermiel, NRR w/enci H. Garg, NRR w/enci Project Mgr., NRR w/enci C. Paperiello, Rill w/enci J. Caldwell, Rlli w/enct B. Clayton, Rlli w/enct SRI Point Beach w/enci DRP w/enci TSS w/enct DRS (2) w/ encl Rlli PRR w/ encl PUBLIC IE-01 w/enci Docket File w/enci GREENS LEO (E-Mall)
DOCDESK (E-Mail)
Endosure 1.
Provide GL 96-01 Project plan procedure.
2.
Provide QA surveillance / audits performed on the GL 96-01 Project.
3.
Provide any CRs and QCRs, technical reviews, and punch list items associated with the number of required service water pumps needed to support accident mitigation
{
evaluations, including potential changes to their initiation logic and loading onto the EDGs.
4.
Provide a list of system / equipment that are considered engineered safety systems.
5.
Provide the EDG loading analysis.
6.
Provide the containment accident fan blade pitch adjustment procedure and the fan break horse power determination following pitch adjustments, including any potential changes to their initiation logic and loading onto the EDGs.
7.
Provide training qualification program for engineering staff and technicians that perform or evaluate logic testing.
8.
Provide the corrective action system procedures.
9.
Provide the design control procedures, including modification and temporary modification procedures.
10.
Provide the procedures used to review industry initiatives, such as NRC Information Notices.
11.
Provide Point Beach response to IN Nos. 88-83,91-13,93-15,93-38,95-15, and any corrective actions.
12.
Provide a list of all LERs and condition reports initiated since 1988 that were associated with logic / contact testing.
13.
Provide the electrical schematics and logic diagrams for the reactor protection system (RPS), EDG load shedding and load sequencing, including interlocks, bypasses, and permissives for each unit.
l 14.
Provide RPS and EDG surveillance procedures that test the logics / contacts, interlocks, bypasses, and permissive contacts for each unit.
15.
Provide RPS calibration and test procedures that implement TS Table 15.4.1-1 for one channel of each trip function identified in TS 15.2.3, including other reactor trips and interlocks for each unit.
16.
Provide a punch list of testing discrepancies identified during the GL 96-01 Project and any other technical reviews performed to assess the GL 96-01 Project.
17.
Provide the technical resolution for each punch list item and any condition reports generated as a result of these reviews.
l
.