ML19323H692
| ML19323H692 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/28/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323H690 | List: |
| References | |
| NUDOCS 8006160060 | |
| Download: ML19323H692 (4) | |
Text
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Isaaco:
Low Temperature Overpressure Protection I
The repair period of 7 days is based on allowing sufficient time to effect repairs i). 3. 2. G There are 3 means of protecting the usinq safe and proper procedures and upon 1.
ECS from overpressurization by a the operability of the redundant PORV.
3.3.2.G pressure transient at low temperatures The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. time period to reach the (below 2500P).
The first type of restrictive conditions in the pressurizer protection is ensured by the operation provides sufficient time to meet these g
and surveillance of the power operated conditions.
g relief valves with a lift setting of his 435 psig.
A single power operated re-The OttS must be treated on a periodic basis consistent with a
lief valve (PORV) will relieve a nres-the need for its use. A channel functional test shall be O
sure transient caused by
- 1) a mass performed prior to enabling the overpressure protection addition into a solid RCS from a charg.-
system during cooldown and startup. This test shall be D
ing pump or
g a reactor coolant pump being started in The channel functional test shall include vert fication of the idle RCS and circulating water into an D
backup air supply.
a steam generator whose temperature is 500F greater than the RCS temperature. (1)
Operability of each low temperature o'ver pressure protection The second means of protection is channel requires the control switch to be in the proper' ensured by a PORv being open.
It will position, the pressure point set, the PORV isolation valves have the same relieving capabilities open, instrument and solenoid power on, and the PORY backup as mentioned above.
. air supply changed, The third means of protection limits the pressurizer level to 25% and the The limitations and surveillance requirements on the ECCS equipment provides assurance that a mass addition prennurizer pronnuro to 100 na19 A
pressure transient caused by the inad-pressure transient can be relieved by the operation of-vertent mass addition from a charging a single PORV or the limiting conditions placed on pump running for 10 minutes will be the pressurizer.
relieved by the large gas volume and low pressure present in the nressurizer The restrictions for startup of a RCP limits the heat as mentioned above.
Itaintaining the input accident to within the relieving capabilities of pressurizer level below 25% will also a single PORV.
make the hi pressurizer level deviation alarm available to the operator during (1) Pressure Mitigating Systems Transient Analysis a mass addition accident.
Results July 1977 Westinghouse Owners Group on RCS Overpressurization.
Amendment No. 54, linit 1 Amendment No. 51, Unit 2 94
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6.6.3.c Special Iteports t
Iteports on the following areas shall be as indicated:
AltEA SUBMITTAI. DATE a.
Primary Coolant Leakage Initial report within one year of initial criti-cality; 5 years after commercial service.
I b.
In-Service Inspection Development First in-service inspection period after initial full power operation.
In-Service Inspection Evaluation The requirements of Section !! ASME Boiler Code c.
(IS-620).
d.
Loose parts monitoring program Onsamedateasin-serviceinspEctionreport.
[
e.
Containment Building Structural Within 90 days following completion of each test.
Tosting Hoport 9
f.
I.nko Michigan Continuing I.ako Study Within 60 days following the end of each 6 month Projects No. 1, 6, 9, 10, 11, 12 ***
routino operating report period. Each report shall contain tabular and firaphical information, analysis and interpretation, of information obtained pursuant to each project.
g.
Waukegan Memorial Airport Expansion The expansion plans and status of such plans for the Plans Waukegan Memorial Airport will be reported yearly in the Annual Report including FAA #5010 report
(
h.
Overpressure Protection System Operation within 30 days of operation.
i
- Zion Nuclear Powor Station Environmental Report, Section 2.3.6, Table 9.
SEPCIAL REPORTS Table 6.6.2 Amendment No. 54, Unit 1 328a Amendment No. 51, Unit 2
a LIF.lTIt;G C0! DIT10N FOR OPERATION SURVEILLANCE REQUIREMENT 3.3 2.
Pressurization and'S"ystem Integrity 4.3 2.
Pressurization and System Integrity A.
IIcatup and Cooldown A.
tio t Applicable The Reactor Coolant System temperature and pressure (with the exception of the pressurizer) shall be limited in accordance with the limit lines shown in Fi gu res 3.3.2-1 and 3.3.2-2 during heatup, cooldown and inservice leak and hydrostatic testing.
1.
Allowable combinations of pressure and temperature for specified temperature change rates are below and of the right of the limit
. lines shown.
Limit lines for cooldown rates between thooc prenen tud may be obtained by interpolation.
2.
Figures 3.3.2-1 and 3.3.2-2 define limita to ansure prevention of non-ductile failure only.
For normal operation other inherent plant characteristics, e.g.,
pump heat addition and pressurizer heater capacity may limit the heatup and cooldown rates that can be achieveJ over certain pressure-tempe ra tu re ranges.
3.
The Reactor Coolant System shall be lindted to a maximum temperature change of 100F/hr during inservice 79 Amendment tio. 50, Unit 1 Amendment fin. 47 lini t
')
?
LIMITit.G CO!1DITION FOR OPERATION SURVEILLANCE REQUIREME!!T r
). 3. 2.
A3.
(Continued) icak and hydrostatic testing operations above the heatup and cooldown limit curves.
B.
The limit lines shown in Figures 3.3.2-1 and 3.3.2-2 shall be recalculated periodically as required, based on results f rom the material surveillance program.
C.
The secondary side of the steam generator must be pressurized above 200 psig if the temperature of the vessel is below 700 F.
s c
D.
The pressurizer heatup rate shall not 0
exceed 100 F/hr and the pressurizer cooldown rate not exceed 200 F/hr.
0 The spray shall not be used if the temperature dif ference between the pressurizer and the spray fluid is 0
greater than 320 F.
C.
Ilydrostatic Testing 1.
System inservice leak and hydrotests shall be performed in accordance with the require-ments of ASME Boiler and Pressure vessel Code,Section XI, 1974 Edition, up to and including Summer 1975 Addendum.
1 80 Amendment tio. 50, Unit 1 n
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