ML20212D399
| ML20212D399 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/23/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton, Tam P Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 2NRC-6-127, TAC-62838, NUDOCS 8612310355 | |
| Download: ML20212D399 (6) | |
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2NRC-6-127 Berrer Vell No. 2 Unit Project organization Telecopy 643-Ext.160 P.O. Box 328 Dec. 23, 1986 Shippingport, PA 15077 Mr. Harolo R. Denton, Director Of fice of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTEN110N:
Mr. Peter Tan, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Secondary Systen Rad Monitoring Change
REFERENCE:
Letter to H. R. Denton from J. J. Carey dated Setember 18, 1986 (2NRC-6-098)
Gentlenen:
Based upon the change described in Reference 1, DLC has been infonnally requested to address redundancy of the subject monitor considering its Regulatory Guide 1.97 type end category.
DLC has detennined that since the primary purpose of secondary systen radiation monitoring is for monitoririg of vented fluids fran stean generator safety valves or atmospheric dump valves, it should be classified as E2 only.
The stean line monitor detectors were designed and manuf actured as Class 1E equipnent.
Because of heat loss, the monitor is not to be used for continuous s anpl ing.
A more direct indication of stean generator (SG) tube rupture is SG level indication. These indications are qualified class 1E and are in continuous operation.
The stean line monitors are qualified to perfonn their RG 1.97 functions.
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United ' States Nuclear Regulatory Commission Mr. Harold R..Denton,' Director Secondary Rad Monitoring Change Page 2 J
The corrected FSAR Sections are attached for your information. These changes will be included in the next FSAR anendment.
DUQUESNE LIGHT COMPANY By t4. y arey 7
Sr. Vice President i
GLB/ijr NR IT/ CHANGE At ients AR N
1 cc:
Mr. Peter Tan, NRC Project Manager i
Mr. J. Beall, NRC Senior Resident Inspector Mr. L. Prividy, NRC Resident Inspector 4
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BVPS-2 FSAR TAALE 7.5-1 (Cont)
Qualification Number Indicator laptementation Power variable Raneeltratus Tvne / C.a t everv Environeemtal Seismic of S.annels Devtee Date (tll Sueolv Conformance Primary Plant 0-350 in A1, D2 Tes Yes 3 per plant 2 meters fuel load IE Tes D'=3T level I channel on plasma display I recorder Auxiliary feedwater 0-400 gpa AI, St. D2 Tes Yes 2 per loop 6 meters fuel load IE Tes flow 3 recorders Core exit 200-23% *F A1, 81, C1 Yes Yes 51 All channels on fuel load IE Tes temperatare plasma display; t
I channel on meter and recorder 7
- Contu=ne::t area IQ*-LO ElRr A1, 51, 12. E2 Tes Yes
- per plant 2 meters fuel load IE Tes
! radiation level
] (high racge) 2 recorders le*P i
_, 3
'j Secondarv system 10 *-10 sci /C:
A1, 52 E2 Tes Yes 1 per plant I anger fuel load IE Tes radiation i
1 recorder RCS suocooling 200*T sub-A2, 52 Tes Yes 2 per plant 2 channels on fuel load IE Tes 4
cooling to i
35*T super-plases display; heated I channel on meter I
l and recorder
} Control rod in/Out 53 No No 1/ rod 1 status complete non-1E*
Tes l posit:on I
light / rod j Neutros flux
]
Lower range I to 10 CPS 81 Yes Yes 2 per plant 2 channels on fuel load IE Tes 6
i f
plasma display; i
I channel on 2
Upper range 0-200*. of power 31 Tes Yes
- per plant 2 channel en recorder fuel load IE Tes plassa display; I
I channel on l
on recorder f AmeM3e=
12 2 of 11 i.
June 1996 I
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BVPS-2 FSAR 7.5.3 Description of Variables 7.5.3.1 Type A Variables Type A variables are defined in Section 7.5.2.2.1.
They are the variables which provide primary information required to permit the main control room operating staff to:
1.
Perform the diagnosis specified in the BVPS-2 EOPs, 2.
Take specified preplanned manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety function to recover from a DBA event (verification of actuation of safety systems is excluded from Type A and is included as Type D), and 3.
Reach and maintain a safe shutdown (hot standby) condition.
Key Type A variables have been designated Category 1.
These are the variables which provide the most direct measure of the information required. The key Type A variables are:
1.
Reactor coolant system pressure (wide range),
2.
Reactor coolant hot leg temperature (T
("' * #*"9'}'
hot 3.
Reactor coolant cold leg temperature (T d) (wide range),
4.
Steam generator level (wide range),
5.
Steam generator level (narrow range),
6.
Pressurizer level, 7.
Reactor containment pressure, 8.
Steamline pressure, 9.
Reactor containment water level (wide range),
10.
Reactor containment water level (narrow range),
11.
Primary plant demineralized water storage tank level, 12.
Auxiliary feedwater flow, 13.
Reactor containment area radiation level, 14.
Core exit temperature, and
/
(55.
Secondary system radfstfon - main steamline radiation Amendment 1 7.5-13
!!ay 1983
BVPS-2 FSAR TABLE 7.5-4
SUMMARY
OF TYPE A VARIABLES Variable Type /
Variable Fdnetion Category RCS pressure (WR)
Key Al RCS hot leg (T
) (WR)
Key Al 3,g RCS cold leg (T mid ) (WR)
Key Al Steam generator Tevel (WR)
Key Al Steam generator level (NR)
Key Al Pressuriner level Key Al I
Containment pressure Key Al Steamline pressure Key Al Containment water level (WR)
Key A1 Containment water level (NR)
Key Al Primary plant DWST level Key Al Auxiliary feedwater flow Key Al Containment area radiation level (HR)
Key Al Core exit temperature Key Al CSecondary syst W ra~diation level Key Al RCS subcooling BacRUji-(P)
A2' il0TES:
WR = Wide range.
NR = Narrow range.
HR = High range.
P = Preferred.
Amendment 1 1 of 1 May 1983 4
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BVPS-2 FSAR TABLE 7.5-9
SUMMARY
OF VARIABLES AND CATEGORIES Variable Type and Category Type Type Type Type Type 3
A B
C D
E RCS pressure (WR) 1 1,2 1,2 2
T
( R) 1 2
hat S/kfNve(WR) 1 2
T l (WR) 1 1,2 2
S/G level (NR) 1 1
2 Pressurizer level 1
1 2
Containment pressure 1
1,2 2
2 Steamline pressure 1
1 2
RWST level 2
Containment water
{
level (WR and NR) 1 1,2 2
2 Primary Plant DWST level 1
2 l
Auxiliary feedwater flow 1
1 2
Containment radiation level (High range) 1 1,2 2
Secondary system - main steamline radiation 2
Core exit temperature 1
1 1
RCS subcooling 2
2
!!eutron flux 1
Reactor vessel level instrumentation system 2
2 Containment isolation valve status 2
2 control rod position 3
containment hydrogen concentration 1
1 Containment pressure (extended range) 1,2 Primary coolant activity 3
Plant vent radiation level 2
2 Site environmental radiation level 3
3 PORV valve status 2
Primary safety valve status 2
Pressurizer heater power availability 2
Charging system flow 2
Letdown flow 2
Volume control tank level 2
Amendment 1 1 of 3
!!ay 1983