3F0288-12, Forwards Response to Encl 2 of NRC Re NUREG-0737, Item II.F.2,including Suggested Clarifications to Discrepancies Noted in Nrc/Ser & Milestones Status
| ML20149J033 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/17/1988 |
| From: | Eric Simpson FLORIDA POWER CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 3F0288-12, 3F288-12, TAC-45124, NUDOCS 8802220246 | |
| Download: ML20149J033 (37) | |
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ee. Power CORPOR AT tO N February 17, 1988 , 3F0288-12 U. S. Nuclear Regulatory Commission ! Attention: Document Control Desk Kashington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 504302 Operating License No. DPR-72 NUREG 0737. Item II.F.2 TAC No. 45124
Dear Sir:
Florida Power Corporation (FPC) is submitting this response in accordance with your letter dated September 10, 1987 Enclosure 2 of your letter is addressed as requested. In addition, FPC noted a few discrepencies in the NRC/SER. Suggested clarifications are provided in Attachment 1. The milestones status as requested in Enclosure 2 of your letter is provided in Attachment 2. The delay in providing this response was coordinated with our Proja;t tianager. Sincerely, hf 'f* E. C. Simpson, Director Nuclear Operation Site .5spport' ECS/EMG/sdr Attachntent xc: Dr. J. Nelson Grace Regional Administrator, Region II Mr. T, F. Stetka Senior Resident inspector h l
'8802220246 880217 k
PDR ADOCK 05000302 P DCD GENERAL OFFICE: 3201 Thirty-fourth Street South
- P.O. Box 14o42
- St. Petersburg, Florida 33733 * (813) 066-5151 A Florida Progress Company
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O O . February 17, 1988 3F0288-12
.ATTAC MENT 1 NRC Letter Clarifications:
- 1. Section 2.2, second paragraph,'second sentence.
Only sixteen (16) core exit thermocouples are recorded on the backup display.
- 2. Section 2.2, fourth paragraph, last . sentence.
The incore probe assemblies were not replaced with quali fied units ' during Refuel V. The modification in Refuel V was to seal the incore detector connectors for the sixteen assemblies that had ~ the core exit thermocouple recorded in the backup display. Sixteen (16) incore probe assemblies were replaced with assemblies that have qualified core exit , thermocouples during the recent outage (Refuel VI). i
- 3. Section 2.3, first paragraph, sixth sentence.
Note that these are not true seal chambers; they are condensate pots. These condensate pots are not sealed and do not have diaphragms or bellows, they are water reservoirs only.
- 4. Section 2.3 l This section infers that we are measuring level where in fact the system is intended to trend reactor coolant inventory.
- 5. Section 2.3, third paragraph, last sentence.
The coolant inventory trending indicators are actually reading between 85 and 90% and pulsating in that range when the reactor coolant pumps are operating. This is due to the system measuring differential pressure across a section of pipe with a moving medium (i.e. reactor coolant flow). I i l
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. t February 17, 1988 i
, 3F0288-12 Page<1 l r I ATTACIMENT 2 : INADEQUATE CORE COOLING INSTRUMENTATION MILESTONES [ Milestone 1 l i Submit Final Design Description (by licensee) (complete the l
- documentation requirements of NUREG-0737, Item II.F.2, including all j plant-specific information items identified in applicable 'NRC evaluation reports for generic aporoved systems). ;
i i Status I l ! ! The Final Design Description including key drawings are provided in - 1 ' attachment 1 and consists of section 7.3.4 and Figures 7-21,22,23,24,25 , of the FSAR. The list of attached drawings are provided in attachment .l
- 3. ~
i Milestone 2 5 Approval of emergency operating procedure (EOP) technical guidelines - (by NRC). ! i l Note: This E0P technical guideline which incorporates the selected system
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must be based on the intended uses of that system as described in i 4 approved generic E0P technical guidelines relevant to the selected i system. j Status 2
- 1) NRC letter dated October 1,1984 provided a review of FPC's Procedures l Generation Package (PGP) for the Emergency Operating Procedures (E0P). "
; That letter requested additional information which was submitted back to the NRC in FPC letter dated July 31, 1985. A revised E0P Writer's Guide was forwarded to the NRC by' FPC letter dated February 4,1988 J
- 2) Attachment 4 provides a list of each ICC Instrumentation Subsystem and implementing procedures.
l Milestone 3 i l Reactor Coolant Inventory Tracking Systems (RCITS) installation complete j (by licensee), i i I I l
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February'17, 1988 ! 3F0288-12 ! Page 2. i Status 3 { FPC letter dated October 23, 1985 (3F1085-12) provided this response as ; part of the implementation report in accordance with NRC letter dated j September 6, 1983, Enclosure 3. The implementation was completed in Refuel V, August 1985. Milestone 4 ! ITS functional testing and calibration complete (by licensee). Status 4
-i ITS functional testing was pe dormed by the MAR that' installed the system, MAR 83-03-04 The construction was completed during the_ last quarter of 1985 and the MAR officially closed on August 26, 1986. ,
l ITS calibration is broken up into three separate surveillance ' procedures-i SP-144A - RCITS Reactor Vessel and Hot Leg Level Channel Calibration; l SP-1448 - RCITS Void Trending Channel Calibration; and j SP-144C - RCITS Core Exit Thermocouple Calibration. l These procedures were last completed on 11/22/85, 9/20/85, and 9/20/85 ' respectively. The functional testing and calibration is therefore complete. Milestone 5 f Prepare revisions to plant operating procedures and emergency procedures based on approved E0P guideline (by licensee). t Status 5 l Attachment 4 provides a list of each ICC Instrumentation Subsystem and I implementing procedures. All E0P's have been revised based upon the l Writer's Guide submitted on February 4,1988. ; I i i l
. O v February 17, 1988 3F0288-12 Page 3 Milestone 6 Implementation letter report to NRC (by licensee).
Status 6 i Florida Power Corporation submitted the implementation letter dated October 23, 1985 (3F1085-12) in which we addressed each of the six (f) implementation letter report content items. l Item (4) of the implementation letter has been revised as follows: l Item (4) Request for modification of Technical Specifications to include all ICC instrumentation for accident monitoring. Revised Response to item (4) l All ICC instruments (along wi th other Regulatory Guide 1.97 instruments) have been evaluated for inclusion in Technical Specifications. This evaluation utilized the criteria for determining the scope of Technical Specifications which is delineated in the NRC Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, issued February 6, 1987. Technical Specification Change Request No.159 was submitted on December 31, 1987 to include the ICC Instrumentation for post accident monitoring. Milestone 7 l l Perform procedure walk-through to complete task analysis portion of ICC system design (by licensee). 1 Status 7 I L Functional and task analysis was performed for the following pertinent l AP's, EP's, and VP's: 1 AP-241 through AP-277 EP-220 VP-580 AP-350 EP-260 l AP-450 EP-200 l AP-530 EP-390 I
s 's e ,y o y_, V Februa ry 17, 1988 i 3F0288-12 Page 4 Milestone 8 Turn on system for operator training and familiarization. Status 8 Operator training was provided by the Training Department at the time each of the four subsystems was installed. ICC operator training has been added to the replacement and requalification programs, l Milestone 9 Approval of plant-specific installation (by NRC). l Status 9 By NRC Milestone 10 Impl ement modified operating procedures and emergency procedures (by licensee). Status 10 Attachment 3 provides a list of each ICC instrumentation Subsystem and in.plementing procedures. l l l
i o V CJ February 17, 1988 3F0288-12 ATTACHMENT 3 FpC Orawings 201-151 Sht 1 Rev. 28 Main Control Board Layout 201-151 Sht 3 Rev. 1 Main Control Board Layout 201 151 Sht 5 Rev. 1 Main Control Board layout FSAR Shts 7-70, 7-70a, Rev. 8 Additional Instrumentation and 7-70b Inadequate Core Cooling FSAR Figures 7-21, 7-22 P.ev. 8 System FSAR Figures 7-23, 7-24 Rev. 7 and 7-25 l Foxboro Drawings l 84N37139-Al-C00 Rev. A RCITS Loop Diagram l 84N37139-Al-C002 Rev. A RCITS Loop Diagram 84N37139-A2-C001 Rev. A RCITS Loop Diagram 84N37139-A2-C002 Rev. A RCITS Loop Diagram 84N37139-A3-C001 Rev. A RCITS Loop Diagram j 84N37139-A3-C002 Rev. A RCITS Loop Diagram 84N37139-A2-C003 Rev B Core Exit Thermocouples l l l l ( I l
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V O V with an accuracy of 5% when used in conjunction with an adjacent backg round detector. The sensitivity of the detector will decrease @f- .j , with exposure to neutron flux due to transmutation of the emitter in the detector. However, by use of integ rated current inventories, it is felt that the additional inaccuracies shall be no more than 1% per year for the average flux conditions. The use of the Incore Monitoring System to detect xenon oscilla-tions is described in B&W Topical Report B AW -10010 , "Stability . Margins for Xenon Oscillations, Part 1 Modal Analysis, Part 2 One-Dimensional Digital Analysis, 'Part 3 Two-and Three-Dimensional Digital Analysis". 7.3.4 ADDITIONAL INSTRUMENTATION - INADEQUATE . CORE COOLING SYSTEM l 7.3.4.1 Design Bases The inadequate core cooling (ICC) system design includes the sub-cooling margin monitors, core exit th e rm oc o u pl e s , and the reactor coolant inventory t r acki ng system (RCITS) incorporating i nv e nt o ry l ev el and void fraction measurements. This system is designed to meet the parameters specified in NUREG-0737, Item II.F.2. The RCITS provides a continuous indication of reactor vessel head and hot leg coolant inventory trending with reactor . coolant pumps either running or tripped. When the pumps are tripped, the cool ant l ev el indicators provide the coolant inventory indication. When the / pumps are running, the void fraction indicators provide inventory (. lev el trend measurement. The entire system is redundant, seismically and environmentally 4 qualified, and powered from Class IE power sources. The indicators are grouped and identified by usage. 7.3.4.2 System Description 7.3.4.2.1 Reactor Coolant Inventory Tracking System The design encompasses the use of differential pressure (DP) measurements across v a rtic al elevations of the hot leg and the [ reactor vessel to infer coolant level when the RCPs are tripped. plus the use of RCP motor power measurements and pump inlet tempera-l tures to infer coolant inventory trends when the RCPs are running. The design also includes density compensation for DP mea su reme n t s due to temperature effects on re f erenc e leg and process liquid density. 7-70 (Rev. 8)
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DP measurements cover a wide range measurement from the top to the bottom of the hot leg, plus a narrow range measurement f rom the top
@ of the reactor vessel (RV) head to the bottom of the hot leg. A total of four DP transmitters are used to provide redundancy. Each pair of wide and narrow range transmitters are powered independently by Cl as s 1E instrumentation power. They are mounted within the cont ai nme nt area. Seal chambers are located at the high point of each ref erence leg to keep the legs full of water.
The design includes removal of the center control rod d riv e mechanism to provide a penetration in the RV head for location of the top RV pressure tap. The top hot leg pressure taps are located off the hot leg high point yents. Class 1E-qu al i fi ed electronic analog equipment racks are used to power the DP transmitters and process their outputs with the reference leg and process temperature outputs to compute the equiva-lent water level. .The racks provide outputs to indicating recorders in the control room and to the computer. A non-1E electronic analog equipment rack is used to process the RCP i nl et temperature and motor power inputs, and to compute the void fraction. The rack provides outputs to a control room indicator recorder and to the computer. , System details are shown in Figures 7-21 through 7-24. N 7.3.4.2.2 Core Exit Th e rmo c'o u pl e s (CET) and Subcooling Ma rg i n l Monitors Three multipen analog temperature recorders are provided on the PSA main control board. A minimum of 16 CETs, four from each core quadrant, are recorded continuously over a range of 0*F to 2,500'F. Two subcooling margin monitors are located on the PSA main control board. These instruments continuously d i s pl ay saturation tempera-ture for each loop. In add i t i on to displaying saturation tempera-ture, each instrument can display, on demand, the hottest CET selected from a group of six CETs. A total of 12 CETs have been selected to provide representative temperatures from each ore quadrant and the control region. These instruments display temptra-tures over a range of 0*F to 1,023*F, well above saturation temperatures. CET system details are shown in Figure 7-25. 7.3.4.2.3 Test and Calibration Test and calibration facilities are built into the RCITS system. The facilitii2 permit an accurate calibration of the systen and detection of system failures in accordance with the requirements of IEEE-279-1968. i 7-70a (Rev . 8)
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7.3.4.3 System Evaluation- . . - - - , (# ' 7.3.4.3.1 System Considerations ' i j Redundant RCITS indications are av ail abl e on the control room PSA i panel. This system is not used [or control but is meant to provide trending of the reactor coolant inventory. 7.3.4.3.2 System Limitations , This system uses four DP transmitters with a common lower connection tap off the decay heat drain line. If this common line f ails, all - the DP measurements in the RCITS are rendered inoperative. b t 1 j i S ) - ; , . -- l l i l i i i i 7-70b (Rev. 8) I I i_. - . . - - . - - _ - . . .
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.? q February 17, 1988 3F0288-12 Page 1 ATTACINENT 4 A list of each ICC Instrumentation Subsystem and its implementing procedure is provided below:
Subcooling Margin Monitoring (SNM) VP-580, Plant Safety Verification Procedure EP-220, Pressurized Thermal Shock EP-290, Inadequate Core Cooling AP-380, Engineered Safeguards Actuation AP-450, Emergency Feedwater Actuation AP-460, Steam Rupture Matrix Actuation AP-580, Reactor Protection System Actuation AP-530, Natural Circulation EP-260, Inadequate Decay Heat Removal EP-390, Steam Generator Tube Rupture AP-990, Shutdown from outside the Control Room All of these procedwes address the use of subcooling margin as an entry condition or a condition requiring operator action. l Core Exit Thermocouples- 1 VP-580, Plant Safety Verification Procedure l EP-290, Inadequate Core Cooling l AP-380, Engineered Safeguards Actuation l EP-220, Pressurized Thermal Shock ' AP-530, Natural Circulation Reactor Coolant Inventory Tracking System (RCITS) AI-704, Reactor Trip Review and Analysis AP-580, Plant Safety Verification Reactor Coolant Pump Void Trend Monitoring System (RCPVTN) AI-704, Reactor Trip Review and Analysis AP-580, Plant Safety Verification With the exception of plant procedure AI-704, all plant procedures were written to the Emergency Operating Procedure guidelines submitted to the NRC for review and approval. A new Wri ter's Guide incorporating NRC Inspection Corrnents, INP0 assist visits, and a Battelle human factors rey'ew has been issued with all E0P's to be rewritten and issued in December, 1987
A February 17, 1988 3F0288-12 Page 2 With regard to the RCITS and RCPVTM, subsystems of Inadequate Core Cooling Monitoring Instrumentation, the following conditions apply:
- 1. The RCPVTM is only functional with Reactor Coolant Pumps operating.
Inadequate Core Cooling would result following loss of subcooling margin and continued plant degradation. On loss of subcooling margin, the immediate operator action is to trip all Reactor Coolant Pumps, thus rendering the instrumentation inoperable. Should RCPs remai n running or require restarting without the required SCM, adequate procedural guidance exists to regain core cooling conditions based on Core Exit Thermocouples and SCM. This data will be analyzed as required by the STA or plant staff personnel .
- 2. The complexi ty of the RCITS information, based on various flow conditions that could exist in the core (forced flow, natural circulation, HPI-PROV cooling, LPI/HPI break cooling, etc), does not allow for real time data analysis for the operator. This data will be analyzed as required by the STA or plant staff personnel.
All four systems have been in service since completion of Refuel V. Documentation of operability can be obtained from applicable surveillance procedures. Training for these systems was covered under the following lesson plans: ROT 4-1, ROT 4-9, ROT 4-11 and RCITS and RCPVTM, was specifically covered during Refuel V.
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