ML20245H891
| ML20245H891 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/28/1989 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20245H889 | List: |
| References | |
| NUDOCS 8903060078 | |
| Download: ML20245H891 (8) | |
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- ATTACHMENT II c.
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Technical Specification Pages Affected by Proposed Amendment No. 130, Revision 1 REMOVE -INSERT 3-30a. 3-30a-3-30b. 3-30b 3-40a ~3-40a-t 3-45 3-45 3-46 3-46 4-18a 4-18a
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h a ~ RANCHO SECO'UNITsl'
>1 . TECHNICAL SPECIFICATIONS-- ,
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, -Limiting Conditions for.. Operation 2, .
- p i 3;6.7 'The Reactor Building purge; valves,~ SFV 53503, SFV 53504,-SFV 53604 .
A. ,
- x ..and.SFV 53605, shall be closed with their respective breakers I< de-energized,'except during cold shutdown or refueling. Valves SFV 5 . 53503 and SFV 53604 shall be' verified:to be in the above condition at least monthly.; The breakers / disconnects on valves SFV 53504 and SFV j _ 53605"sha111be verified to;be de-energized at least monthly.
3
' 3.6.81 The Reactor Building purge' valves and Reactor. Building pressure ./
equalization valves sha11' isolate on high containment. radiation, level. See Table 3.5.1-1 for operability requirements.
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f Bases
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The reactor _ coolant system conditions of cold shutdown assure that no steam wil1~be formed:and hence no' pressure buildup in the. containment if the reactor-coolant system' ruptures.
The selected shutdown' conditions are based on the type of activities that are q
.being carried out and will-preclude criticality in any occurrence. ;
n' The Reactor Building is designed for an internal pressure of,59 psig and an.
- g .externalcprescure 2.0 psi. greater;than the internal-pressure. The' design ]
external pressure: corresponds to the differential ~ pressure thatlcould be-developed.if the building is sealed with an' internal temperature of 120*F with 11 a barometric: pressure of 29.0 inches of Hg and the' building is subsequently
@ ' cooled to ;an internal; temperature of 80*F. with'a concurrent rise-in barometric ~
pressure to 31.0-. inches of Hg.
When containment inte'grity is established,-the limits of 10 CFR 100 will not be exceeded should'the maximum' hypothetical accident occur.
The 0PERABILITY T of"the containme'nt ' isolation' ensures that the containment - 1 atmosphere will be isolated fror. the outside environment in the event of a, 1 release of radioactive material to the containment atmosphere by pressurization--
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of the containment. Containment isolation within the'-time limits'specified j ensures that the release of radioactive material to the environment will be~ 1 consistent:with the assumptions used.in the analyses for LOCA. l 1
Specifications 3.6.7 and 3.6.8 are in response-to NUREG 0737, item II.E.4.2.
u REFERENCES
- l. "
t- (1) USAR, section 5
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s Proposed 3 Amendment No. 37, 49, 87, 130, Revision 1 3-40a t , . >
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! RANCHO SECO UNIT 1 l
TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.8.8 When two irradiated fuel assemblies are being handled simultaneously within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times. Irradiated fuel a:semblies may be handled with the auxiliary bridge crane provided no other irradiated fuel assembly is being handled in the fuel transfer canal.
3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.
3.8.10 The Reactor Building purge system, including the Reactor Building Stack radiation monitor, shall be tested and verified to be operable within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to REFUELING OPERATIONS and once per 7 days during REFUELING OPERATIONS.
3.8.11 Hith the Reactor Building purge system or the Reactor Building Stack radiation monitor inoperable, close each of the Reactor Building purge system penetrations which provide direct access from the Reactor Building atmosphere to the outside atmosphere.
3.8.12 No loads will be handled over irradiated fuel stored in the spent fuel pool, except the fuel assemblies themselves. A dead weight load test at the rated load will be performed on the Fuel Storage Building handling bridge prior to each refueling.
3.8.13 Irradiated fuel shall not be removed from the reactor until the unit l has been subtritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Bases Detailed written procedures will be available for use by refueling personnel.
These procedures, the above specifications, and the design of the fuel handlina equipment, as described in Section 9.8 of the USAR, incorporating .
bui~ t-in interlocks and safety features, provide assurance that no incident !
could occur during the refueling operations that would result in a hazard to public health and safety. If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation.
Continuous monitoring of radiation levels and neutron flux provides immediate indication.of an unsafe condition. The decay heat removal pump is used to maintain a uniform boron concentration.2 The refueling boron concentration indicated in Specification 3.8.4 will be maintaineo to ensure that the more restrictive of the following reactivity conditions is met:
- 1. Either a keff of 0.95 or less with all control rods removed from the core.
- 2. A boron concentration of 11800 ppm.
Proposed Amendment No. 29, 77, 79, 86, 130, Revision 1 3-45 !
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation The actual calculated boron concentration for item (1) above is 1974 ppm boron. Specification 3.8.5 allows the control room operator to inform the Reactor Building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing Reactor Building purge termination is to verify that these components will function as required should a fuel handling accident occur that results in the reletse of significant fission products.
Specification 3.8.13 is required because the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shut down for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and all 208 fuel pins in the hottest fuel assembly fail, releasing all gap activity.2 The requirement that at least one DHR loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during REFUELING OPERATION, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two DHR loops OPERABLE when there is less than 37 feet of water above the core ensures that a single failure of the operating DHR loop will not result in a complete loss of decay heat removal capability.
With the reactor vessel head removed and 37 feet of water above the core, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating DHR loop, adequate time is provided to initiate emergency procedures to cool the core.
REFERENCES (1) USAR, Section 9.5 (2) USAR, paragraph 14.2.2.3.2 Proposed Amendment No. 29, 77, 87, 130, Revision 1 3-46
,y DL #
. ; RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.'.1.2.3 4 (Continued) ]
(d) The Containment purge. valves shall be t'ested at least once every 6 months. The Containment equalization valves shall be tested at least once every 3 months.
(e) ..The Containment-purge valves shall be tested prior to the initial purge on each cold shutdown and prior to reaching hot shutdown during heatup for a return 'to operation. A test conducted for this section may be-applied to satisfy the requirement for a-6-month test of section (d) above if it is conducted within that interval. If the equalization valves are not tested with the purge valves under this section, their 3-month-test requirement must still be met.
(f)' At least once per 31 days ~ by ' verifying that all penetrations not capable of being closed by OPERABLE.
containment automatic isolation valves and required to be closed during accident conditions are closed by.
valves, blind flanges, or deactivated automatic valves secured'in their positions.
Exceptions to this are those valves listed in Table b
3.6-1, and any other valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed.or otherwise-secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOHN except-that such verification need not be performed more often than once per 92 days.
Proposed Amendment No. II, 49, 56, 97, 130, Revision 1 4-18a
~ ~
.,- RANCHO SECO UNIT-1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM l-Sampling -Minimum Analysis Type of Activity Lower Limit Gaseous Release Frequency Frequency- . Analysis of Detection Type (LLD) (a)
(uCi/ml)
A. Haste Gas P _P Principal Gamma 1 x 10-4 Storage Tank Each Tank Each Tank Grab Emitters (f)
Sample
- B. Reactor Building P P. . .
Purge and Each Purge Each Purge . .
Principal Gamma 1 x 10-4 Equalization and Equal- and Equalization Emitters (f)
Vent ization . Vent (b,e,1)
Vent Grgb-Sample (D,9,1) H-3 1 x 10 . C. Auxiliary M(b,c.e) M(b) Principal Gamma 1 x 10-4 Building Stack. Grab Emitters -(f)
Sample H-3 1 x 10-6 D. Auxiliary M(b) M(b) Principal Gamma 1 x 10-4 Building Grade Grab Emitters (f)
Level Vent Sample H-3 1 x 10-6 E. All. Release Continuous H(d) 1-131 1 x 10-12 Types as listed Charcoal in A,B,C.D above Sample Continuous H(d) 1 Particulate Principal Gamma 1 x 10-11 Sample Emitters (f)
(I-131. Others)
Continuous M Gross Alpha (h) 1 x 10-11 Composite Particulate Sample Sr-89, Sr-90(g) 1 x 10-11 Continuous Noble Gas Noble Gases 1 x 10-4 Monitor Gross Beta and
- Gamma as Xe-133 Proposed Amendment No. 53, 98, 130, Revision 1 4-75
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