ML19210D900
| ML19210D900 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/16/1979 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Thomas C NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| References | |
| NUDOCS 7911280377 | |
| Download: ML19210D900 (68) | |
Text
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GENER AL OFFICE P. o. Box 499 COLUMBUS, NEBR ASKA 68601 Nebraska Publ.ic Power Distr.ic t TETE ~o~e m s.4 8sei November 16, 1979 Mr. C. O. Thomas Bulletins & Orders Task Force U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Thomas:
Dur:.nz the July 12, 1979 meeting between the GE BWR Owners Group and the NRC Bulletins & Orders Task Force, several plant-unique Systems Group questions were deferred to a later date. Enclosed please find Nebraska Public Power District's response to these deferred questions.
It should be noted that complete in-house review and verification has not yet been completed for all of the information provided. If oTr final review determines that any of the enclosed information is in-correct, the correct information will be immediately st.bmitted.
If you have any questions regarding the enclosed, please do not hesitate to contact me.
Sincerely,
.. Pilant Director of Licensing and Quality Assurance JDW/cmk Enclosure cc: P. W. Marriott (GE) w/o drawings
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1402 029 7911280 g @f.
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PLANT Cooper Nuclear Station BYPASS CAPACITY Plant Steam Bypad Capacity, ", Rated 25 1/02 1 030 9
PLANT Cooper Nuclear Station SYSTEMS AND COMPONENTS SHARED BETWEEN UNITS PAGE 1 CONTINUED PAGE -
Single-unit plant check here x and do not complete 1402 03)
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PLANT Cooper Nuclear Station PLANT-SPECIFIC SYSTEM INFORMATION General Water Sources Instrumentation and Control Frequency of Safety Seismic Safety Seismic Safety Seismic Sys. tem and System Classification Category Classification Category Classif. Category Component Tests
- 1. RCIC N.S.R. I S.R. (Note A) I N.S.R. II SAAT=R, P&VOT=M FRT=Q
- 2. IIPCI S.R. I S.R. (Note A) I S.R. I S AAT=R, P&VOT=M FRT=Q
- 3. LPCS N.A. (Note B) N.A. N.A. S AAT=R, P&VOT=M, FRT=Q
- 4. LPCI Part of RilR System Modes (See Item 7) - -
S AAT=R, P&VOT=M, FRT=Q
- 5. ADS (Note C) N.A. N.A. S.R. I (Note L) SAAT=R
- 6. SRV S.R. I N.A. N.A. S.R. I (Note L)
- 7. RilR (Including shutdown cool-ing, steam condens- - S.R. I S.R. (Note D) I S.R. I P&VOT=Q, FRT=Q ing, suppression pool cooling, con-tainment spray modes)
- 8. Service Water (SW) S.R. I (Noto E) (Note K) P&VOT=M, FIrr=Q
- 9. RBCCW (Note F) (Note K) P&VOT=M, FRT=Q
- 10. CRDS (Note G) N.S.R. II S.R. I (Note M)
- 11. CST (Note 11) N.S.R. II S.R. I None
- 12. thin Feedwater (Note I) N.S.R. II N.S.R. II Nono
- 13. Recirculation
__, Pump / Motor Cooling N.S.R. II (Note J) II N.S.R. II None
_2s (13 Legend: S.R. - Safety Related M = Once/ Month rs) N.S.R. - Non-Safety Related Q = Once/3 Months N.A. - Not Applicable R = Once/ Operating Cycle (or each refueling)
C23 SAAT = Simulated Automatic Actuation Test h(j P&V0T = Pump and Valve Operability Test
. . FRT = Flow Rate Test i
9.
Note A - For HPCI and RCIC Systems, water sources are either the Torus (Suppression Pool) or the Emergency Condensato Storage Tanks located in Basement of Control Building.
Note B - CNS has a Core Spray System (CS) which has the characteristics identical to those listed for the RHR System Hote C - Piping upstream of SRV's is safety related and Seismic Category I. Piping down-stream of SRV's is not safety elated and Seismic Category II Note D - Water source is the Torus (Suppression Pool)
Note E - Water source is the river (Missouri). Classification does not apply.
Note F - RBCCW System is divided into essential portion (safety related, Seismic Category I) and a non-essential portion (non-safety related, Seismic Category II). The boundaries are delineated on the System Flow Diagrams (DWG 2031 attached).
Note G - CRD System is divided into safety related, Seismic Category I and non-safety related, Seismic Category I . The boundaries are delineated on the System Flow Diagram
, (DWG 2039 attached). Watar source is from the Condensate Storage Tank.
Note H - Condensate Storage Tank (CRT) is Seismic Category II, not safety related. Water source is domineralized water from Flant Make-up System.
Emergency Condensate Storage Tank is Seismic Category I, safety related. Water source is from the Condensato Storage Tank.
Note I - i4ain Feedwater is Seismic Category II, not safety related, from Hotwell (Main Condenser) to Steam Tunnel.
From Steam Tunnel to Reactor Pressure Vessel, System is safety related, Seismic Category I.
Water sourco is from the Condensate Storage Tank m Note J - Cooling Water Supplv is from the RBCCW System (Note F).
m c3 Note K - SW and RBCCW SysPems are composed of safety and non-safety related categories, r0 Instrumentation and controls required for safety related functions have been qualified for Seismic Category I service.
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Note L - Italf of the SRV's are bench checked once per operating cycle. All SRV's are tested every two cycles.
Note M - Each operable control rod is exercised one notch once each week when >30% power.
Scram time tests = R. 10% of the CRD's are scram time tested at 16 week intervals.
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cs PRIllARY C0flTAINMENT ISOLATION SYSTEM DATA h] PAGE /9 CONTINUED ON PAGE FINAL o
tn ,
ABBREVIATIONS ra Engineered Safety Function Isolation Valve Type Isolation Signal Codes (utility supply)_.
N = NO B = Butterfly Code Parameter (s) Sensed Set Y = YES BCK = Ball check or Group 1 Isolation Point (un.
BL = Ball Position Indication in Control Room CK = Check (laI*""**'* ' "" *"'"O T b
. DCV = Diaphragm 1 d ect n rol Vahe GB = Globe N = None Others stated in Table l ef SCV = Stop Check Fluid SV = Solenoid A = Air VB = Vacuum Breaker S = Steam XV = Explosive W = Water Others stated in Table Others stated in Table gyc y = e xe . W.w ciec1 v ,/,.
Isolation Valve Location Isolation Valve Power Source I = Inside Containment A = Air 0 = Outside Containment AC = AC Others stated in Table DC = DC >
11 = Hand I_s_olation Valve Actuation Mode P = Process fluid A = Au toma tic Others stated in Table OP = Overpressure RF = Reverse Flow RM = Remr,te Manual Others stated in Table '
Y;
Isolation VaI'vle,'Eo<si0'" tions 6 Isolation Valve Actuator AI = As Is A0 = Air C = Closed M0 = Motor 0 = Opcn 50 = Solenoid Others stated in Table Others stated in Table Lc t,c c L eJ cbs e)
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V. CU N I A 1.VibN 1' lbOLA11UN Onuurd Group I Isolation Signals:
- 1. Reactor low water level > -37")
- 2. Main steam line low pressure (jt 50 8 psin) and mode switch in RUN
- 3. Main steam line area high temperature (12000F)
- 4. Main steam line high radiation (13 x normal full power background)
- 5. Main steam line high flow (1 140% of rated flow)
. 6. Main condenser low vacuum (jt 7" hg)
Group II Isolation Signals
- 1. Reactor low water level (> +12.5")
- 2. High drywell pressure (< +2 psig)
Group III Isolation Signals
. 1. Reactor low water level (>+12.5")
- 2. RWCU system high flow (1 200% of system rated flow)
- 3. RWCU system high area temperature (1 2000F)
Group IV Isolreion Signals ,
- s. HPCI steam line high flow (;1300% of rated)
- 2. HPCI steam line area high temperature (;1 200 F)
- 3. HPCI steam line low pressure (> 100 psig)
- 4. Manual isolation pushbutton (Only if initiation signal exists)
Groun V Isolation Signals .
- 1. RCIC steam line high flow (1300% of rated)
- 2. RCIC steam line area high temperature (1 200 F)
- 3. RCIC steam line low pressure (> 50 psig) g .,
,JJ
- 4. Manual isolation pushbutton
uroup vt Isolation Signals
- 1. Group II isolation input; i.e.: High drywell pressure (< +2 psig) or low reactor water level (y_ &l2.5") or
- 2. Reactor Building vent exhaust high radiation (1 100 mr/hr)
(Tech. Spec. limit)
Group VII Isolation Signals i
- 1. Reactor lov water level (?_ -37")
- 2. Main steam line high radiation (;1 3 x normal full power background) 14.02 0154 4
9
v NOTES:
- 1. These valves if shut will open on a system initiation signal.
- 2. These valves open in shutdown when using thic RHR Loop for shutdown cooling.
- 3. Drywell ventilation control system is isolated, providing maximum cooling to drywell.
- 4. These valves are kept closed except when required to operate the valve inside containment.
- 5. These lines were for instruments used for LPCI Loop Select logic.
These instruments have been removed and the lines isolated at the penetration.
- 6. ACAD system is kept isolated due to not being approved by the NRC '
for use at this time.
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PLANT Cooper Nuclear Station DESIGN REQUIREMENTS FOR CONTAINMENT ISOLATION BARRIERS Question: Discuss the extent to which the quality standards and seismic design classification of the containment iso-lation provisions follow the recommendations of Regula-tory Guides 1.26 " Quality Group Classifications and Standards for Water, - Steam, - and Radioactive-Water-Containing Components of Nuclear Power Plants" and 1.29
" Seismic Design Classification".
Response
A. Quality Standards The containment isolation valves and process piping included between these valves which penetrates containment constitute the isolation pro-visions addressed in this response. The design, f abrication, erection, inspection, and testing of the piping and valves comply with the quality standards of USAS B31.7, Class I and the applicable quality standards of the ASME Code,Section III, Class B, respectively.
An exception to this is the main steam piping which was constructed to USAS B31.1.0 since it was the applicable code in effect at the time the piping was ordered. However, by invoking additional nondestructive inspection requirements applied in compliance with applicable ASME Code and ASTM standards, the quality level was upgraded to comply with the intent of quality Group B as defined in Regulatory Guide 1.26.
For the B31.7 piping, a Code Inspector Certified USAS B31.7 NP-1 Data Report for Nuclear Piping was completed and filed for each piping system.
The containment penetrations were designed, fabricated, erected, inspected and testing in accordance with the requirements of Section'III, Class B except that the process pipe included in the penetration assembly complies with USAS B31.7, Class I.
On the basis of the above, the quality standards applied to the containment isolation piping and valves comply with the intent of Group B quality standard of Regulatory Guide 1.26 which is recommended for these isolation provisions.
B. Seismic Design Classification The containment isolation piping valves were designed to withstand the effects of a Hypothetical Maximum Earthquake (now referred to as a Safe Shutdown Earthquake - SSE). They were classified in the design as Class IS (now referred to as Seismic Category I). The components were qn2 080
designed, f abricated and erected to withstand the effects of an SSE without loss of capability to perform their safety functions (i.e. , to safely shut-down the reactor and maintain it in a safe shutdown condition).
The quality standards applied in the design of Class IS components utilized the codes and standards delineated in paragraph A above.
Quality assurance programs were specified and applied to the design, f abrication, erection and testing of the components. These programs comply with the intent of the applicable sections of Appendix B of 10CFR50, 1102 089 e
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PLANT Cooper Nuclear Station PROVISIONS FOR TESTING Question: Discuss the design provisions for testing the operability of the isolation valves.
Response
- 1. All motor or air operated valves which are required to function on an isolation or system initiation are tested at least monthly to insure operability and the stroke times are checked quarterly.
- 2. All primary containment boundary valves have the provision for leak rate testing and are tested each refueling outage.
- 3. All excess flow check valves on instrument lines in use are tested each refueling outage to verify their ability to limit flow.
- 4. All check valves which are required to open on an initiation and are located in inaccessible areas are equipped with air operators for testing the valves. They also have a free floating disc and will open or close if required regardless of the position of the air cylinder.
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PLANT Cooper Nuclear Station CODES, STANDARDS AND GUIDES Question: Identify the codes, standards and guides applied in the design of the containment isolation system and components.
Response
The isolation system consists of the containment isolation valves and piping included between the valves which penetrates containment. The codes and standards applied in the design are as follows:
- 1. Piping - USAS B31.7 except for the main steam piping which applied USAS B31.1.0. Additional nondestructive inspection requirements were applied to the main steam piping which upgraded the quality level to comply with the intent of quality Group B of Regulatory Guide 1.26. The containment penetrations were designed to Section III, Class B.
- 2. Valves - The " Pressure-Temperature Ratings" given in USAS B16.5 were applied in conjunction with specified fabrication and in-spection requirements utilizing ASME and ASTM specifications.
Welding involked ASFE IX. The inspections and testing utilized constitute compliance with the intent of the applicable require-ments of ASME Section III, Class B.
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PLANT Cooper Nuclear Station NORMAL OPERATING MODES AND ISOLATION MODES Question: Discuss the normal operating modes and containment isolation provision and procedures for lines that transfer potentially radioactive fluids out of the containment.
Response
There are two lines which carry potentially radioactive fluids out of the containment. These lines exit through penetrations X-18 and X-19. These are from the drywell equipment drain sump and the drywell floor drain semp, respectively. The isolation valves for these lines are normally kept open and the pumps are started when it is desired to transfer fluid to the radioactive waste tanks. The isolation valves are air operated valves which fail shut. These valves are closed by a group II isolation.
Af ter the conditions which caused the isolation have been corrected, the switches for the isolation valves are first placed in the closed position.
The isolation will then be reset. If there is indication of a high activity in drywell, chemistry and health physics personnel will be notified and at their request, a small amount of water will be pumped for analysis prior to placing the systems back in service. If drywell atmosphere activity is normal, the valves may be reopened.
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