ML19322B352
| ML19322B352 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/12/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B351 | List: |
| References | |
| NUDOCS 7912020198 | |
| Download: ML19322B352 (10) | |
Text
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Or 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, AND REACTOR BUILDING SPRAY SYSTEMS Apolicability Applies to the emergency core cooling, reactor building cooling, and reactor building spray systems.
Objective To define the conditions necessary to assure immediate availability of the emergency core cooling, reactor building cooling, and reactor building spray 3
systems.
m-Specification 3.3.1 The following equipment shall be operable whenever there is fuel in the reactor vessel and reactor coolant pressure is 3S0 psig or greater or reactor coolant temperature is,2500F or greater:
(a) One reactor building spray pump and its associated spray nozzle header.
(b) Two low pressure service water pumps for Units 1 and 2, and two low pressure service water pumps for Unit 3.
The valve in the discharge from the reactor building cooler (LPSW 108, 2LPSW 108, and 3LPSW 108) shall be locked open.
(c) A and B Engineered Safety Feature low pressure injection pumps shall be operable.
(d) Two low pressure injection co61ers shall be operable.
(e) Two BWST level instrument channels shall be operable.
(f) The borated water storage tank shall contain a minimum level of 46 feet of water having a mimimum concentration of 1,800 ppm 0
boron at a temperature not less than 40 F.
The manual valve, LP-28, on the discharge line from the borated water storage tank shall be locked open.
(g) The two reactor building emergency sump isolation valves shall l
be either manually or remote-manually operable.
(h) Two reactor building cooling fans and associated cooling units.
(i) The Engineered Safety Features valves associated with each of the above systems shall be operable.
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3.3.2 In addition to 3.3.1 above, the follm.ing ECCS equipment shall be operable when the reactor coolant system is above 350*F and irradiated fuel is in the core:
(a) Two high pressure injection pumps shall be maintained operable to provide redundant and independent flow paths.
(b) Engineered Safety Feature valves and interlocks associated with 3.3.2a above shall be operable.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operable when the reactor coolant system is above 800 psig:
(a) The two core flooding tanks shall each contain a minimum of 13 i 3
.44 ft. (1040 1 30 ft ) of borated water at 600 1 25 psig.
(b) Core flood'ing tank boron concentration shall not be less than 1,800 ppm boron.
(c) The electrically-operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
(d) One pressure instrument channel and one level instrument channel per core flood tank shall be operable.
3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3.2, and 3.3.3 is operable.
(a) The other reactor building spray pump and its associateu spray nozzle header.
(b) The remaining reactor building cooling fan and associated cooling unit.
(c) Engineered Safety Feature valves and interlocks associated with 3.3.4a and 3.3.4b shall be operabic.
3.3.5 Except as noted in 3.3.6 below, tests or maintenance shall be allowed during power operation on any component (s) in the high pressure in-jection, low pressure injection, low pressure service water, reactor building spray or reactor building cooling systems which will not remove more than one train of each system from service, Components shall not be removed from service so that the affected system train is inoperable for more than 24 consecutive hours.
If the system is not restored to meet the requirements of Specification 3.3.1, 3.3.2, 3.3.3, or 3.3.4, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the requirements of Specification 3.3.1, 3.3.2, 3.3.3, or 3.3.4 are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a condition below that reactor coolant system condition required in i
Specification 3.3.1, 3.3.2, 3.3.3, or 3.3.4 for the component degraded.
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,g 3.3.6 Exceptions to 3.3.5 shall be as follows:
s (a) Both core flooding tanks shall be operational above 800 p (b) Both motor-operated valves associated with the cure flood tanks shall be fully open above 800 psig.
(c)Onepressureinstrumentchannelandonelevelinstrumen per core flood tank shall be operable above 800 psig.
(d) One reactor building cooling fan and associated cooling un be permitted to be out of service for seven days provided both reactor building spray pumps and associated spray nozzle hea are in service at the same time.
3.3.7 Prior to initiating maintenance on any of the components, cate (redundant) component shall be tested to assure operabilit the dupli-:
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be made critical, adequate engineered safety fea 1
n high pressure injection pumps and two low pressure injection pumps Two specified.
However, only one of each is necessary to supply emergen coolant to the reactor in the event of a loss-of-coolant accident inventory to reflood the core.(1) core flooding tanks are requi (h
Both The borated water storage tanks are used for two purposes:
(a) As a supply of borated water for accident conditions.
(b) As a supply of borated water for flooding the fuel transfer ca refueling operation.(2) nal during Three-hundred and fif ty thousand (350,000) gallons of borated water (a level of 46 feet in the BWST) are required to supply emergency core c reactor building spray in the event of a loss-of-core cooling accident n
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This amount fulfills requirements for emergency core cooling s
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water storage tank capacity of The borated 388,000 gallons is based on refueling v l requirements.
Heater's maintain the' borated water supply at a temperature o ume to prevent freezing.
The boron concentration is set at required to maintain the core 1 percent subcritical at 70 F without a the amount of boron control rods in the core.
minimum value specified in the tanks is 1,800 ppm boron.This con The spray system utilizes common suttien lines with the low pressure i jection system.
If a single train of equipment is removed from either n-
- system, the other train must be assured to be operable in each syste m.
When the reactor is critical, maint'enance is allo fI on 3.3.5 operability of the duplicate components.
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sure Operability of the specified com-
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4 ponents shall be based on the results of testing Specification 4.5.
if the operability of equipment redundant to thaThe maintenanc demonstrated immediately prior to removal ceptable t removed from service is
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likelihood of failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followingThe basis of acceptabili such demonstration.
Ithasgeenshownfortheworstdesignbasisl 14.1 ft be exceeded with one spray and two coolers op~rablh (a
pressure will not maintenance period of seven days is acceptable for e
e.
Therefore, a cooling fan and its associated cooling unit.(3) one reactor building
' In the event that the need for emergen of one train (one high pressure injection pumpcy core cooling should occur pump, and both core flooding
, one low pressure injection a main coolant loop severence, tanks) will protect the core and in the event of 2,3000F and the metal-water reaction to that replimit the peak clad tem
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1 resenting less tha 1 percent low pressure service water pumps serve OconeThree conee Units 1 and 2 and two pressure service water pump per unit.is required fcros e Unit 3.
There is a manual
, 2, and 3.
One low normal operating requirements are greater than th or normal operation.
The following a loss-of-coolant accident e emergency requirements REFERENCES (1) FSAR, Section 14.2.2.3 (2) FSAR, Section 9.5.2 l
(3) FSAR, Supplement 13 i
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3.14 PENETRATION ROOM VENTILATION SYSTEMS Applicability Applies to the penetration room ventilation systems.
Objective To define the conditions necessary to assure immediate availability of the penetration room ventilation systems.
Specification t
3.14.1 Two trains of the penetration room ventilation systems shall be operable at all times when containment integrity is required or the reactor shall be shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with the following exception:
If one of two trains of a penetration room ventilation system is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding l
seven days provided that all active components of the other train of the penetration room ventilation system shall be demonstrated to be operable'within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and daily there-after.
Bases A single train of reactor building penetration room ventilation equipmen retains full capacity to control and minimize the release of radioactive materials from the reactor building to the environment-conditions.
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i 3.15 HYDROGEN PURGE SYSTEM Applicability Applies to the Reactor Building Hydrogen Purge System.
Objective To define the conditions necessary to assure the availability of the Reactor Building Hydrogen Purge System.
Specification If the Reactor Building Hydrogen Purge System should become inoperable, it shall be restored to an operable status within 7 days or the Oconee Units shall be shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Bases The hydrogen purge system is composed of a portable purging station and a portion of the Penetration Roob Ventilation System.
The purge system is operated as necessary to maintain the hydorgen concentration below the control limit. The purge discharge from the Reactor Building is taken from one of the Penetration Room Ventilation System penetrations and discharged to the unit vent. A suction may be taken on the Reactor. Building via isolation valve PR-7 (Figure 6-5 of the FSAR) using the existing vent and pressurization connections.
The analysis to determine the effect on the incremental doses at the site boundary, resulting from purging hydrogen from the reactor building following a postulated LOCA, requires that the purge be started at 460 hours0.00532 days <br />0.128 hours <br />7.60582e-4 weeks <br />1.7503e-4 months <br /> (19.2 days) following the LOCA to limit hydrogen concentration to 4% by volume.
If the Hydrogen Purge System is determined to be inoperable, the requirement to restore the system to an operable status within 7 days will provide reasonable assurance of its availability in the event of a LOCA.
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4.4.3 HYDROGEN PURGE SYSTEM Applicability Applies to the Reactor Building Hydrogen Purge System.
Objective To. verify that the Reactor Building Hydrogen Purge System is operable.
Specification 4.4.3.1 Operating Tests An in-place system test shall be performed annually.
This test shall consist of a visual inspection, hook-up of the system to g
one of the three reactor buildings, a flow measurement using flow instruments in the portable purging station and pressure drop i
measurements across the filter banks.
This test shall demonstrate I
th t under simulated emergency conditions the system can be taken from storage and placed into operation within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The annual test shall insure the fallowing:
Pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches of water at the system design flow rate (+10%).
Operability of the heater at rated power when tested in.
accordance with ANSI N510-1975.
Additional testing requirements are as follows:
l Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any.
structural maintenance on the system housing.
4 Halogenated hydrocarbon testing shall be performed after each complete or partial replacement or the charcoal adsorber bank.
or after any structural maintenance on.the system housing.
The results of the in-place cold DOP and halogenated' hydro-carbon tests at design flows on HEPA filters and charcoal adsorber banks shall show >99% DOP removal and >99% halogenated hydrocarbon removal when tested in accordance with ANSI N510-197S
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,The results of laboratory carbon sample analysis from the 1
ihydrocarbon purge system carbon shall show >90% radioactive methyl iodine removal when tested in accordance with ANSI N510-1975 (1300C, 95% R.H.).
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f The System shall be operated with the heaters on at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
Fans shall operate within +10% of design flow when tested in accordance with ANSI N510-1975.
In addition to the annual testing requirement, the tests and analyses shall be performed following painting, fire or chemical release in any ventilation zone communicating with the system.
t Bases Pressure drop across the combined HEPA filters and charcoal adsorbers of
'less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter. A test frequency of once per year establishes system r
performance capability.
m, High efficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers o
are installed to reduce the potential release of radioiodine.
Bypass leakage for the charcoal adsorbers and particualte removal efficiency for HEPA filters are determined by halogenated hydrocarbon and DOP respectively. The laboratory carbon sample test results indicate a radioactive methyl iodide removal efficiency for expected accident conditions. Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the perfomances are as specified, the calculated doses wonid be less than the guidelines stated in 10 CFR 100 for the accidents analyzed.
The frequency of tests and sample analysis are necessary to show that the i
HEPA filters and charcoal adsorbers can perfom as evaluated.
Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52.
The charcoal adsorber efficiency test procedures should allow for l
the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples.
should be at least two inches in diameter and a length equal to theEach sample thickness of the bed.
If the iodine removal efficiency test results are unacceptable, all adsorbent in the system should be replaced.
j Any HEPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system every month will demonstrate oper:3ility of the filters and adsbrber system. Operation for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is used to reduce the moisture uilt up on the adsorbent.
If painting, fire or chemical release occurs such that the HEPA filter or
-charcoal adsorber could become contaminated from the fumes foreign chemicals or as require'd for operational usematerials, the same tests and sample analysis sh 1
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PENETRATION ROOM VENTILATION SYSTEM 4.5.3 Applicability Applies to testing of the. Penetration Room Ventilation System.
Objective To verify that the Penetration Room Ventilation System is operable.
Specification At least once per operating cycle, or once every 18 months, whichever occurs first, the following conditions shall be 4.1.2.1.1 f
demonstrated:
Pressure drop across the combine ~d HEPA filters and charcoa j
adsorber banks is less than 6 inches of water at the system a.
design flow rate (+10%).
Automatic initiation of each branch of each penetration room b.
ventilation system.
Manual operability of the bypass valve for filter cooling.
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The tests and analysis for the penetration room ventilation system or once shall be performed at least once per operating c 4.1.2.1.2 fire or chemical release system operation of following painting, in any ventilation zone communicating with the system.
Cold DOP testing shall be performed after each complete or partial replacement of a HEPA filter bank or after any structural mainten on the system housing.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing.
The results of the in-place co,1d DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall show >99% DOP removal and >99% halogenated hydrocarbon removal respectively when tested in accordance with ANSI N510-1975.
The results of laboratory carbon sample analysis shall show >90%
radioactive methyl iodide removal when tested in accordance with ANSI N510-1975 (130 C, 95% R.H.).
0 Fans shall be shown to operate within +10% design flow when tested in accordance with ANSI N510-1975.
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Each circuit shall be operated at least 15 minutes every month.
Bases Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
A test frequency of once per operating cycle establishes system performance capability.
High efficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging cf the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential release of radioiodine.
Bypass leakage for the charcoal adsorbers and particulhte removal efficiency for HEPA filters are determined by halogenated hydrocarbon and DOP respectively.
The laboratory carbon sample test results indicate a radioactive methyl iodide removal efficiency for expected accident conditions. Operation of the fans significantly different from the design flow will change the removal efficiency of,the HEPA filters and charcoal adsorbers.
If the performances are as specified, the calculated doses would be less than the guidelines stated in 10 CFR 100 for the accidents analyzed.
The frequency of tests and sample analysis are necessary to show that the HEPa filters and charcoal adsorbers can perform as evaluated.
Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52.
The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two sampics. Each sample should be at 1 cast two inches in diameter and a length equal to the thickness of the bed.
If the iodine removal efficiency test results are unacceptabic, all adsorbent in the system should be replaced. Any HEPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.,
Operation of the system every month will demonstrate operability of the filters and adsorber system. Operation for 15 minuter demonstrates operability and minimizes the mnisture build up during testing.
If painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sakple analysis should be perfon.ed as required for operational use.
Demonstration of the automatic initiation capability is necessary to assure system performance capability.
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