ML20235X972
| ML20235X972 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/21/1987 |
| From: | Beatty G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RNPD-87-2862, NUDOCS 8707250007 | |
| Download: ML20235X972 (5) | |
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CP&L 4
Carolina Power & Light Company in22mmit:3steermarterram ROBINSON NUCLEAR PROJECT DEPARTMENT POST OFFICE BOX 790 HARTSVILLE, SOUTH CAROLINA 29550 JUL 2 1 1987 Robinson File No:
13510 Serial:
RNPD/8?-2862 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 LICENSE NO. DPR-23 1986 CHANCES TO THE FACILITY REPORT
Dear Sir:
Carolina Power and Light Company (CP&L) furnishes the enclosed list of changes te the facility as described in the Final Safety Analysis Report pursuant to 10CFR50.59.
If you have any questions concerning this report, please contact me.
Very truly yours, 0hN MCC Cuy P. Beatty, J.
Vice President H. B. Robinson S. E. Plant RDC:jch Enclosure cc:
H. E. P. Krug J. N. Grace B707250007 9797g3 f
DR ADOCK 05000261 PDR I \\
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1986 i
H. B. ROBINSON UNIT NO. 2 CHANCES, TESTS, AND EXPERIMENTS PURSUANT TO 10CFR50.59 1.0 As permitted by 10CFR50.59(a)(1), changes were made at HBR that changed l
the facility as described in the Updated Final Safety Analysis Report, but did not constitute unreviewed safety questions. They did not i
require changes to the Technical Specifications or revisions to the i
Technical Specifications were not required prior to initiation. The changes did not adversely affect the safety of the Plant or health and safety of the general public. The changes were as follows:
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l 1.1 Security CCTV cameras, gate monitors, microwave, and E-field intrusion equipment was relocated, installed, and tested. A high mast lighting fixture was added, lighting poles were modified, and security lighting was rewired. This modification involved security equipment only, and did not affect the operation of safety-related equipment (M-705).
1.2 Piping was added to provide the capability to hook up an external i
l hydrogen recombiner into the existing Post Accident Containment Venting I
l System (PACVS).
This system utilizes the existing PACVS containment l
penetration to supply and return containment gases. This modification l
did not affect the operability of the PACVS valves required for reactor I
criticality by the Technical Specifications (M-750).
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1.3 The Auxiliary Electtical Distribution System was modified in order to I
j provide a reliable source of off-site power to the safety-related equipment fed from 480V Emergency Buses El and E2.
In addition, this modificat sn improved the voltage regulation on the emergency buses, i
decreased the available fault current on the 480V system, increased the capacity of the BOP buses, and decreased the heat loading in the 4.16KV l
switchgear room. Two new Station Service Transformers (SST-2F and SST-2C) were installed which serve the emergency buses only. This modification ensures that the Auxiliary Electrical Distribution System l
loading is adequate under postulated LOCA conditions (M-360).
1.4 The Generator Hydrogen Gas Dryer was replaced with a new Dual Tover l
Dryer. This new dryer has'four times the amount of dessicant, which l
provides more drying capacity. The new dryer has an automatic reactivation and does not have to be removed from service for reactivation of the dessicant. Thus, this gives continuous drying and assures generator protection at all times. A service water supply of two gallons per minute and an instrument air supply for the dryer were provided. This is a vendor recommended replacement unit (M-829).
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'Page 2 of 4 1.5 An addition to the 4160V and 480V distribution system was required to provide electrical power to the new Radwaste Facility and Crystallizer System. This addition censisted of a new 4160V switchgear line-up to the existing bus, and adding a 2000KVA 4160V to 480V transformer and 480V switchgear. The electrical equipment installed is not safety-related.
It was determined that the basis for Technical Specification 3.7 should be changed to reflect the correct number of 4160V and 480V buses. The load addition to the Electrical Distribution System was evaluated and found to be acceptable (M-851).
1.6 The Unit 2 Start-Up Transformer (S.U.T.) was disconnected from the west 115KV bus and reconnected to the span bus between a new second bus sectionalizing breaker. This arrangement enables the S.U.T. to be supplied from either of the two 115KV buses, thus improving the reliability of offsite power to the nuclear unit. This modification also upgraded the existing breaker failure scheme between the west bus auto-transformer 115KV breaker and the 230KV breakers 52-5 and 52-6.
This change improved the reliability of the breaker failure scheme, thereby increasing overall station security (M-899).
1.7 A second set of 115KV BCTs were connected in parallel with the BCTs used in the Start-Up Transformer Differential Circuit. This modification was implemented because of an analysis that revealed that the 115KV BCTs in the Start-Up Differential Relay Circuit could have become saturated due to high current flowing through the transformer.
The modified BCT connections provide a more accurate current signal to the start-up transformer differential relays, improving the security of the relay protection scheme. No new equipment was added.
- However, minor wiring changes were made in the start-up transformer control panel (M-889).
i 1.8 The Letdown Line Relief Valve (CVC-203) was replaced with two relief valves of different sizes and set pressures to allow smooth operation 1
of the valves over the entire range of possible flowrates in the letdown line. Needle valves were installed in the air lines to the letdown orifice isolation and letdown line containment isolatien valves to control their opening and closing rates and to eliminate two sources of letdown line relief valve actuation. The letdown orifice isolation valves were relocated away from the regenerative heat exchanger and upstream of the letdown orifice. These facility changes have relieved maintenance problems associated with u.ese valves and have reduced the radiation exposure associated with maintenance of these valves (M-812).
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'Page 3 of 4 1.9 The Condensate Storage Tank (CST), which had been damaged due to overpressurization, was restored to full operability per original specifications. In addition, this repair eliminated the possibility of CST overpressurization due to excessive condensate flow, Inadequate CST overflow, or both. The CST capacity, described in the FSAR as 200,000 gallons, was changed to 190,000 gallons. A restriction orifice was installed in the Hotwell dump line to prevent overpressurization (M-862).
1.10 The undervoltage relay circuitry and the degraded voltage protection relay circuitry of Emergency Buses El and E2 were modified. This change improved the reliability of the emergency buses to maintain power to the emergency switchgear. This modification was initiated by the loss of an offsite power event on January 28, 1986. This modification increased the reliability of emergency bus operation, increased the dependability of safety-related power sources, and did not degrade the normal undervoltage and degraded grid protection circuitry (M-890).
1.11 Redundant level loops for the Refueling Water Storage Tank (RWST) and the Containment Spray Additive Tank (SAT) were added to provide.
redundant RTGB level indication for each tank. Transmitter impulse lines connect to the tank process lines in the same manner as the existing transmitters. These transmitters and indicators are seismically qualified for their respective mounting locations. All equipment is environmentally qualified for the area of the Plant in which it is located. Both loops are associated with Protection Set III in order to provide separation from the existing RWST and CAST level I
loops (M-864).
1.12 The addition of a closed fire door between the switchgear room and the l
battery room required modifying the HVAC system in order to provide a means to control battery room temperature and to alleviate the possibility of hydrogen buildup. This modification consisted l
of: closing the HVS-1 battery room air outlets, closing the existing exterior wall fan opening, adding two fresh air inlets, and adding two exhaust fans on the exterior wall. Annunciation of the exhaust air l
flow and fan operation is in the control room. This mo'dification provides a redundant means of supplying the required air flow for hydrogen removal, and maintains room temperature by the addition of two l
cooling units (M-445M).
1.13 Moisture removal equipment was installed to the turbine crossunder lines at the exit of each of the four high pressure turbine exhaust i
nozzles. The purpose of this equipment is to remove a significant I
portion of moisture from the steam to eliminate the potential for-erosion / corrosion in the turbine crossunder lines (M-877).
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- Page 4 of 4 1.14 Two new systems were installed for storage of waste oil and solvents.
The Contaminated Waste Oil Storage system will store radioactively contaminated waste liquids, and the Noncontaminated Waste Oil Storage system is used to store noncontaminated liquids. These systems do not tie in to any existing eperating radioactive waste system. Equipment for each system is constructed to prevent liquid release in the event of a piping or tank rupture. These new storage systems are not safety-related (M-840).
1.15 A change was made in the Steam Generator Blowdown System Modification modification. This modification changed globe valves in the SCBD penetrations to double disk gate valves (CWP-747).
l 1.16 Instrument loops P-444 and P-445 for the pressurizer pressure control channels were rewired so that all signals leaving the Hagan Rack come from the output of the isolating modules. This corrected a deficiency in that if a circuit was broken anywhere, such as the indication or recorder on the RTCB, the complete control loop would be defeated.
1 This would cause the loop to go full on with the pressurizer heaters and full off with the pressurizer spray.
In addition, the PORV for the 1
failed loop would be out-of-service. With this facility change, Instrument loops P-444 and P-445 are more reliable for Plant control j
(EE 86-148).
1.17 A two-inch Aluminum, polymer coated service watcr line to the Hydrogen
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Side Seal Oil Cooler was replaced with a 316L stainless steel pipe.
This piping was replaced due to corrosion. Through an evaluation of-the service water system, stainless steel piping was determined to be the most appropriate replacement, in that the low carbon content precludes the sensitization conducive to microbiologically induced corrosion (EE 86-052).
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