ML15084A179
| ML15084A179 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/23/2015 |
| From: | Glover R Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-049, EA-12-051, RNP-RN15-0025 | |
| Download: ML15084A179 (4) | |
Text
J_~ DUKE R. Michael Glover H. B. Robinson Steam
~ ENERGYe Electric Plant Unit 2 Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0 : 843 8571704 F: 843 857 1319 Mike.G/ovet@duke-energy.conr Serial: RNP-RN15-0025 MAR 2 3 2015 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23
Subject:
Mitigating Strategies Onsite Audit Results for Orders EA-12-049 and EA-12-051 Ladies and Gentlemen:
The purpose of this letter is to communicate Duke Energy's understanding of the Mitigating Strategies Onsite Audit results that were discussed by the audit team during the NRC exit meeting on March 6, 2015. The attached enclosure provides a table showing the status of the 88 items identified in theSE Tracker as discussed during the audit team exit meeting with H. B. Robinson personnel. Item status is identified as open, closed, or pending.
Duke Energy is requesting that the NRC advise H. B. Robinson of any differences between status shown in the enclosure and the results presented during the team exit so that plans can be initiated to ensure that there will be minimal impact following the start of the H. B. Robinson implementation outage and receipt of the audit report.
Should you have any questions regarding this submittal, please contact Mr. Richard Hightower, Manager, Nuclear Regulatory Affairs at (843) 857-1329 .
Sincerely, R. Michael Glover Site Vice President RMG/shc
Enclosure:
Status of SE Tracker Items from NRC Onsite Audit cc: Ms. M. C. Barillas, NRC Project Manager, NRR Mr. K. M. Ellis, NRC Sr. Resident Inspector Mr. V. M. McCree, NRC Region II Administrator Mr. J. C. Paige, NRC Mitigating Strategies Project Manager, JLD
U. S. Nuclear Regulatory Commission Enclosure to Serial: RNP/RA-15-0025 Page 1 of 3 ENCLOSURE Status of SE Tracker Items from NRC Onsite Audit Reviewer ltemiD Status Remarks Armstrong & Scales (2-A) 01 3.2.4.8.A 0 Pre-staged portable diesel generators Armstrong (61-B) 0 Protected source of SG makeup using AFWP and debris removal to access connections.
Paige (9-A) Cl 3.1.5.2.A p Calculation NAI-1801 Miller (11-A) CI3.2.1.B p WCAP-17601-P & additional justification Heida {22-A) CI3.2.3.A p Containment pressure & temperature analysis Multiple (24-A) Cl 3.2.4.2.A p Heat Up Cales to address equipment functionality and personnel habitability Heida {19-B) p Cont. Temperature and Pressure against the cont. design limits.
He ida (20-B) p Cont. temperature and pressure during ELAP Heida {33-B) p Effects of loss of ventilation and cooling on Main Control Room during ELAP.
He ida {68-B) p Provide Cont. Analysis & Computer Codes for developing Cont. response to ELAP.
Miller (1-A) 01 3.2.1.8.B c RCS Boration Equipment Paige (3-A) Cl 3.1.1.1.A c Permanent FLEX Storage Building Design Paige (4-A) CI3.1.1.2.A c Debris Removal Equipment is protected Paige (5-A) Cl 3.1.1.2.B.1 c Haul Routes reviewed for soil liquefaction Paige (6-A) Cl 3.1.1.2.B.2 c , Ensure connection points are protected and key areas are accessible
!Armstrong & Scales (7-A) CI3.1.1.3.A c Procedure for local instrument readings and equipment operation without control power.
Paige {8-A) CI3.1.1.4.A c : Review status of the RRC Playbook Armstrong & Miller (10-A) CI3.2.1.A c Identify Cales from WCAP-17601-P and PWROG-14064 for 3-LP W Reactors Armstrong {12-A) CI3.2.1.C c SG PORVs motive force and protected Armstrong (13-A) CI3.2.1.E c SDAFW steam trap availability during ELAP Miller {14-A) CI3.2.1.1.A c Application of NOTRUMP code for ELAP Miller (17-A) Cl 3.2.1.3.A c Use decay heat model for all purposes.
Decay heat model includes heat from actinides Miller (18-A) Cl 3.2.1.6.A c Revised amalysis based on low-leakage seals Miller (19-A) Cl 3.2.1.6.B c PWROG Interim Core Cooling Position Paper Miller & Armstrong {21-A) Cl 3.2.1.9.A c Review hydraulic analysis, portable pump connections and review locations for FLEX Pumps and water sources.
Rx sys review primacy system injection equip.
Armstrong {23-A) Cl 3.2.4.1.A c Cooling water supply to permanent equip. for ELAP Mitigation.
He ida (25-A) Cl 3.2.4.2.B c Adequate ventilation to Battery Rooms Armstrong & Miller (26-A) Cl 3.2.4.3.A c Effects of loss of heat tracing.
Potential for boric acid precipitation or freezing in equipment used for primarY makeuQ.
Paige (27-A) Cl 3.2.4.4.A c Determine if communications assessment is reasonable.
U. S. Nuclear Regulatory Commission Enclosure to Serial: RNP/RA-15-0025 Page 2 of 3 Reviewer ltemiD Status Remarks Multiple (28-A) CI3.2.4.7.A c Prioritization of water sources.
Armstrong (29-A) Cl 3.2.4.9.A c Refueling strategy for FLEX equipment.
Scales (30-A) CI3.2.4.10.A c Review load calcs for FLEX DG and walkdown.
Multiple (32-A) CI3.3.1.A c EPRI Maintenance & Testing guidance for FLEX equipment Paige (1 ~B) c Soil liquefaction (see 5-A above)
Multiple (2-B) c SG portable pumper location and hose route.
SFP cooling portable pump location.
Armstrong (3-B) c Power supplies needed to move FLEX equip.
Internal flooding mitigated by site Paige (4-B) c characteristics. No gravity drain at RNP. No AC power is required to mitigate groundwater.
Service Water system in the RAB is robust.
Paige (6-B) c l!..ake level is controlled by spillway gates.
Paige (7-B) c Ensure debris removal equip. is protected.
Paige (8-B) c Ensure debris removal equip. is protected.
Paige (9-B) c Review FSG-005 if com[>lete.
Paige (10-B) c Lake has never frozen. Review FSG-005.
Paige (11-B) c Review analysis of HVAC equipment.
Paige (12-B) c HVAC requirements for operating equipment.
Miller (16-B) c Attempt to restore seal cooling.
0-rings in RCPs are material 7228-C or better.
Paige (24-B) c Mitigating Strategies for Shutdown & Refueling Heida (30-B) c SFP venting provided by door and roof hatch.
Armstrong (31-B) c SFP makeup strategy.
Analysis or technical evaluation to demonstrate Heida (32-B) c adequacy of ventilation to support equip.
op_eration thro!Jgt.l all phases of ELAP.
Multiple (34-B) c Ventilation for Battery Rooms Multiple (36-B) c Additional portable lighting will be available.
Paige (37-B) c Modifications to fences, structures to facilitate deployment of FLEX equipment.
Miller (38-B) c Current strategy for cooling reactor cannot rely on RWST, because it may_be destroyed.
Scales (40-B) c Address appropriate electrical isolations and interactions in procedures.
Armstrong (41-B) c Availability of fuel storage for ELAP.
Scales (43-B) c Calculations & detailed load shedding strategy Multiple (52-B) c How many valve operations & in what environmental conditions.
Heida (54-B) c Battery Room ventilation Paige (57-B) c Use EPRI Maintenance & Testing for FLEX equipment.
Armstrong (58-B) c UHS use as part of FLEX makeup to SGs.
Armstrong (60-B) c Prioritization of SFP makeup water sources.
Multiple (62-B) c Manual operation of steam supply valves.
Miller (63-B) c Portable boratiolil tanker output water quality.
Multiple (64-B) c Non-safety related circulating water inlet bay.
He ida (65-B) c Ventilation in SDAFW Pump room.
Scales (66-B) c Calculations & load shedding strategy.
U. S. Nuclear Regulatory Commission Enclosure to Serial: RNP/RA-15-0025 Page 3 of 3 Reviewer Item ID Status Remarks Armstrong & Miller {69-B) c Motive force on AOV operators {see 12-A)
Armstrong & Miller {70-B) c Evaluate impact on Thermal-Hydraulic analysis.
Scales {1-0) c Provide clear sketch of SFP w/dimensions.
Scales {2-0) c Loading on mounting device & connections.
Scales {3-0) c Seismic testing of SFP Instrumentation.
Scales {4-0) c Mounting attachments for instrumentation.
Scales {5-0) c Reliability and testing of installed equipment.
Scales {6-0) c For #5 above results of test to demonstrate qualificatio171 and reliability.
Scales {7-0) c Independence of signals and displays.
Scales {8-0) c Calc showing battery backup duty cycle.
Scales {9-0) c Instrument channel accuracy and maximum allowed deviation from design accuracy.
Scales {10-0) c Testing, calibration, preventive maintenance and surveillance duration for instrumentation.
Scales . {11-0) c Location of instrument channel display.
Scales {12-D) c Procedure to address operation, calibration, test, maintenance and inspection process for SFP instrumentation.
Scales {13-D) c Maintenance and testing program, and compensatory actions.
Miller {1-E) c Confirm water solid RCS will not be permitted.
Miller {2-E) c ELAP calculations with NOTRUMP Miller {3-E) c Timeline to Reflux cooling Miller {4-E) c Water source and filtration capability.
Miller {5-E) c Suction strainer design.
Miller {6-E) c Human Factors are applied to FLEX Strategies.
Scales {7-E) c RFI/EMI impact of SFP level Instrumentation.
Open (0)- Some additional action needed from licensee.
Pending (P)- NRC has the necessary information, agrees with the licensee direction but needs to complete review of information.
Closed (C)- NRC accepts licensee response, no further action required by licensee.