ML023240304

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License Amendment Request: Surveillance Requirement Frequency for Containment Spray Nozzle Inspections - Response to Request for Additional Information
ML023240304
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/07/2002
From: Cooper D
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB4282
Download: ML023240304 (7)


Text

Committed to NuclearExcellen Palisades Nuclear Plant Operated by Nuclear Management Company, LLC November 7, 2002 U S Nuclear Regulatory Commission 10 CFR 50.90 ATTN: Document Control Desk Washington, DC 20555-0001 PALISADES NUCLEAR PLANT DOCKET 50-255 LICENSE DPR-20 LICENSE AMENDMENT REQUEST: SURVEILLANCE REQUIREMENT FREQUENCY FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB 4282)

By letter dated March 1, 2002, Nuclear Management Company, LLC (NMC) requested Nuclear Regulatory Commission (NRC) review and approval of a license amendment for the Palisades Nuclear Plant. NMC proposed to revise Appendix A, Technical Specifications (TS) for the containment spray nozzle inspection surveillance requirement (SR) 3.6.6.9 frequency to "Following maintenance which could result in nozzle blockage" rather than at the currently specified 10-year frequency.

On October 7, 2002, the NRC issued a request for additional information (RAI) in relation to the above license amendment request. Enclosed is NMC's response to the RAI.

SUMMARY

OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.

Do las E. Cooper Site Vice-President, Palisades CC Administrator, Region III, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Enclosure 27780 Blue Star Memorial Highway

  • Covert, MI 49043 Telephone- 616.764 2000

ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC PALISADES PLANT DOCKET 50-255 NOVEMBER 7,2002 LICENSE AMENDMENT REQUEST:

SURVEILLANCE REQUIREMENT FREQUENCY FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 5 Pages Follow

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS PALISADES NUCLEAR PLANT NUCLEAR REGULATORY COMMISSION (NRC) REQUEST- INTRODUCTION By application dated March 1, 2002, the Nuclear Management Company, LLC (the licensee), submitted a request to change Technical Specification (TS) 3.6.6.9 to allow performance of the surveillancerequirementfor the containment spray nozzle inspection "following maintenance which could result in nozzle blockage"ratherthan at the currently specified 10-year frequency. Pleaseprovide the following additional information:

NRC REQUEST

1. Experience at the Donald C. Cook NuclearPlant (D.C. Cook), Unit 1, seems to indicate that boric acidplate-out with the potentialto block flow through the containment spray headersand nozzles can occur following an inadvertentspray actuation.' (see Licensing Event Report (LER) 98-027-02).

(a) Has Palisadesever had an inadvertent actuation of containmentspray?

NUCLEAR MANAGEMENT COMPANY (NMC) RESPONSE There were two inadvertent actuations on July 19, 1984 (see Licensee Event Report (LER) 84-011-00). The actuations were a result of personnel errors made while performing containment pressure switch calibrations. An estimated 1000 to 3000 gallons of borated water were sprayed into the containment building during the event. No spray actuations have occurred since this event.

NRC REQUEST (b) If yes, what type of inspection of the spray system piping and nozzles was done and what other steps were taken to ensure that no boric acid build-up occurred?

NMC RESPONSE Following the 1984 actuation, containment cleanup activities were performed. No documentation can be found to confirm that a formal inspection was conducted of the spray system piping and nozzles at that time. Procedurally, the spray headers are required to be drained and refilled with demineralized water following an actuation. The subsequent

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS PALISADES NUCLEAR PLANT surveillance inspections performed in 1987 and 1992, as documented in the March 1, 2002, submittal, confirm that the spray system piping and nozzles have remained free from obstruction.

NRC REQUEST (c) If no, what type of inspection would be done following an inadvertent spray actuation? Why is this method sufficient to detect blockage due to boric acid plate-out?

NMC RESPONSE N/A NRC REQUEST

2. Experience at D. C. Cook, Units 1 and 2, seems to indicate that the typical test for blockage in the containment spray lines and nozzles may not be effective in detecting debris in the spray lines, at least the amount reported in LER 98-027-02.

Do your testing records for Palisadesshow any evidence that the TS-required containment spray flow blockage test may have a sensitivity to debris in the lines or nozzles which is too low (i.e., debris is present but not detected by this test)? For example, has construction debris or other debris been found in the containment spray system as a result of later inspections, tests, or repairwork other than the containmentspray system blockage test requiredby the TSs?

NMC RESPONSE Palisades testing records do not show any evidence that the TS-required containment spray flow blockage test may have a sensitivity to debris in the lines or nozzles which is too low. The spray nozzle tests that have been performed previously have not shown evidence of construction debris in the system. The tests revealed the system is unobstructed. Maintenance and inspection activities, which have required opening of other system components, have not revealed any debris.

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS PALISADES NUCLEAR PLANT NRC REQUEST

3. Describe any previous maintenanceactivities on the containment spray system that had the potentialto introduce debris. What assuranceis there that no such debrispresently exists (includingdebris from construction)?

NMC RESPONSE The containment spray system (CSS) and the low pressure safety injection (LPSI)/shutdown cooling systems (SDC) have had various types of maintenance during the life of the plant. This includes opening and reclosing of pumps and valves. NMC has a foreign material exclusion program that has proven effective in keeping foreign material out of these safety related systems. Various ASME Section Xl Inservice Tests, ISI pressure test activities and various maintenance activities provide assurance that no foreign material presently exists in these systems.

NRC REQUEST

4. With respect to the foreign materialexclusion (FME)controls at Palisades:

(a) Describe how the FME controls would prevent debris from remainingin the containmentspray system piping, headers, and nozzles following maintenance, testing, or inspections which result in opening the system.

NMC RESPONSE The FME program at Palisades contains elements, such as physical barriers or the use of lanyards, to assure foreign material does not enter the system. The FME program establishes barriers around systems that are going to be opened and controls materials entering and exiting those areas. If any discrepancy occurs, the corrective action process is initiated to research the scope of the issue, determine what actions are necessary to return the area to the required level of cleanliness and determine whether testing is necessary. These elements are an integral part of the work order process.

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS PALISADES NUCLEAR PLANT NRC REQUEST (b) Why are the FME controls sufficient, following any maintenance,testing, or inspections that results in opening the system, to ensure that nothing remains in the system sufficient to block the system and cause a decrease in spray flow?

NMC RESPONSE Final inspections, prior to reclosure, ensure that materials and tools brought to the maintenance site are removed and that the system is clean.

Work practices, such as verification checklists, are used to ensure the system is clean prior to closure so that nothing remains in the system sufficient to block the system and cause a decrease in spray flow.

NRC REQUEST

[c] Why should a blockage test not be run to provide increasedassurance that the containmentspray system is still capable of performing its safety function after the system is opened?

NMC RESPONSE In addition to the previous responses, 4(a) and 4(b), the spray headers are not subjected to flow from the CSS or the LPSI/SDC systems. The nozzles are kept dry and therefore free from borated water, which would create a corrosive environment. These headers are isolated by a control valve when operability is required and by a control and manual valve during shutdown periods. These actions provide increased assurance that the containment spray system is still capable of performing its safety function after the system is opened.

NRC REQUEST

5. Following maintenance on a component of the containment spray system, what specific criteriaare used to determine whether a flow blockage test of the containment spraysystem is required? Who makes the decision?

What level of management approves this decision?

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR CONTAINMENT SPRAY NOZZLE INSPECTIONS PALISADES NUCLEAR PLANT NMC RESPONSE Maintenance activities associated with the containment spray system, or any safety class system, procedurally requires that a pre-maintenance inservice inspection (ISI) review be performed. The appropriate ISI pressure testing requirements are validated during this review. The ISI pressure testing requirements are initially determined during the maintenance planning process. Following maintenance on the CSS, any condition adverse to quality would result in a condition report. The condition would be evaluated on a case-by-case basis. If required, a nozzle test would be specified and performed. The condition report would trigger an operability determination and corrective actions. Corrective actions require approval of assigning and accepting by department managers. Additionally, increased outage scope, such as to perform a flow blockage test, requires approval of plant management.