NLS2018063, Submittal of 10 CFR 50.55a Relief Request PR5-02 Supplement
| ML18319A095 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/08/2018 |
| From: | Dent J Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2018063 | |
| Download: ML18319A095 (7) | |
Text
Nebraska Public Power District Always there when you need us 10 CFR 50.55a NLS2018063 November 8, 2018 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
10 CFR 50.55a Relief Request PR5-02 Supplement Cooper Nuclear Station, Docket No. 50-298, DPR-46
Reference:
Letter NLS2018061 dated November 5, 2018, from John Dent, Jr., Nebraska Public Power District (NPPD) to Nuclear Regulatory Commission (NRC),
"10CFR 50.55a Relief Request PR5-02"
Dear Sir or Madam:
The purpose of this letter is for NPPD to supplement the emergent relief request made on November 5, 2018 (Reference).
Relief Request PR5-02 will be used only for the duration of Refueling Outage 30. The information requested by the NRC in relation to the referenced letter was provided via email on November 5, 2018. This same information is attached to this letter.
This letter contains no regulatory commitments.
Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
Sincerely,
~1ff£1<- ~ /w?" ~J f1"' ~
John Dent, Jr.
Vice President Nuclear and Chief Nuclear Officer
/tf
Attachment:
Cooper Nuclear Station Relief Request PR5-02 Supplemental Information COOPER NUCLEAR STATION P.O. Box 98 /Brownville,. NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com
NLS2018063 Page 2 of2 cc: Regional Administrator w/attachment USNRC - Region IV Cooper Project Manager w/attachment USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/attachment USNRC-CNS NPG Distribution w/o attachment CNS Records w/attachment
NLS2018063 Attachment Page 1 of 5 Cooper Nuclear Station Relief Request PRS-02 Supplemental Information Cooper Nuclear Station (CNS) understands that the relief being requested is applicable only to Refueling Outage 30 and not for the entirety of the fifth 10 year inservice inspection interval. Any additional period(s) outside of CNS Refueling Outage 30 would require subsequent, stand-alone, relief requests.
The specific components for which relief is being requested are listed in the tables on the next page.
Drawings describing the location of the components for which relief is being requested have also been included as part of this attachment.
For the portions of piping operated at or above reactor pressure during normal operation that are not at test pressure, defense-in-depth for detection of possible through-wall leakage is provided by the following:
- The temperature alarm subsystem of leak detection system is comprised of temperature sensing elements installed in the vicinity of residual heat removal (RHR), reactor water cleanup (RWCU), high pressure coolant injection (HPCI),
reactor core isolation cooling (RCIC), and main steam lines (MS), and temperature switches that actuate annunciators in the Control Room. It is designed to detect leaks in the major steam piping system, especially in remote or enclosed areas such as the steam tunnel. If a steam or water leak occurs, the temperature element would sense a rise in ambient temperature and cause an alarm in the Control Room. In addition, the continuous temperature signals are transmitted to Plant Management Information System (PMIS) for Safety Parameter Display System (SPDS) display.
- Control Room operators monitor Main Steam Tunnel temperatures twice per shift (every six hours) and record in Operations Log when temperature exceeds 160 F.
- Drywell unidentified and identified leak rates are monitored in accordance with Operations daily surveillance log every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
NLS2018063 Attachment Page 2 of 5 CNS PRS-02 Lists of Components Valves not in position required for normal reactor startup:
Position Required Position During Valve Description for Normal Reactor System Leakage Startup Test Outboard Feedwater RF-CV-13CV Open Closed Check Valve Inboard Feedwater RF-CV-14CV Open Closed Check Valve Outboard Feedwater RF-CV-15CV Open Closed Check Valve Outboard Main MS-AOV-A086A Steam Isolation Open Closed Valve Outboard Main MS-AOV-A086B Steam Isolation Open Closed Valve Outboard Main MS-AOV-A086C Steam Isolation Open Closed Valve Outboard Main MS-AOV-A086D Steam Isolation Open Closed Valve Inboard HPCI Steam HPCI-MOV-M015 Open Closed Supply Outboard HPCI HPCI-MOV-M016 Open Closed Steam Supply Inboard RCIC Steam RCIC-MOV-M015 Open Closed Supply Outboard RCIC RCIC-MOV-M016 Open Closed Steam Supply Other valves discussed in Relief Request:
Position Required Position During Valve Description for Normal Reactor System Leakage Startup Test Inboard Main Steam MS-MOV-M074 Open/Closed Open Drain Valve Outboard Main MS-MOV-M077 Open/Closed Open/Closed Steam Drain Valve HPCI Injection Check HPCI-CV-29CV Closed Closed Valve Inboard Feedwater RF-CV-16CV Open Open Check Valve
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