ML20209G516
| ML20209G516 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/27/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20209G389 | List: |
| References | |
| NUDOCS 8702050380 | |
| Download: ML20209G516 (11) | |
Text
LIMITING CONDITIONS FOR OPERATION BORON CONCENTRATION 3.1.1.2 The boron concentration of the coolant in all filled portions of the Reactor Coolant System shall be maintained between 4350 and 6000 ppm and at a temperature above 50*F.
APPLICABILITY: RECOVERY MODE ACTION:
If either of the above conditions are not satisfied (Boron Concentration between 4350 and 6000 ppm and temperature above 50*F) immediately suspend all activities involving CORE ALTERATION or the Reactor Coolant System and take action in accordance with Specification 3.0.3 to restore the concentration to l
within acceptable limits.
3.1.1.3 The boron concentration of the water in all filled portions of the Fuel Transfer Canal (deep end) and the Spent Fuel Storage Pool "A" shall be musntained between 4350 and 6000 ppm.
APPLICABILITY: RECOVERY MODE ACTION:
If the above condition is not satisfied (Boron Concentration between 4350 and 6000 ppm), take action necessary to restore the boron concentration to within acceptable limits.
3.1.3 CONTROL ASSEMBLIES MECHANISMS 3.1.3.1 Deleted.
8702050300 870127 DR ADOCK 0500 0
THREE MILE ISLAND - UNIT 2 3.1-2
LIMITING CONDITIONS FOR OPERATION 3.4 REACTOR COOLANT SYSTEM
-REACTOR COOLANT LOOPS 3.4.1 Deleted.
REACTOR VESSEL WATER LEVEL MONITORING 3.4.2 As a minimum two independent reactor vessel level monitoring instruments shall be OPERABLE.
APPLICABILITY: RECOVERY MODE WITH THE RV HEAD REMOVED ACTION:
a.
With only one reactor vessel level monitoring instrument OPERABLE, terminate all activities involving changes in the reactor coolant system water volume, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
b.
With no reactor vessel level monitoring instrument OPERABLE, terminate all activities involving changes in the reactor coolant system water volume.
Restore the system to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SAFETY VALVES 3.4.3 Deleted.
3.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 3.4.9.1 The Reactor Coolant System shall be maintained between a Tavg of less than 200*F and greater than 50*F.
3.4.9.2 The Reactor Coolant System shall remain open to the reactor building atmosphere unless repressurization is approved in a safety evaluation submitted to the NRC.
This safety evaluation shall specify the maximum pressure limits and overpressure protection that is required.
THREE MILE ISLAND - UNIT 2 3.4-1
LIMITING CONDITIONS FOR OPERATION 3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION 3.8.2.1 The following A.C. electrical busses listed in Section 4.8.2.1 of the REC 0VERY OPERATIONS PLAN shall be OPERABLE and energized with tie breakers open (unless closed in accordance with site-approved procedures) between redundant busses.
APPLICABILITY:
REC 0VERY MODE ACTION:
With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
THREE MILE ISLAND - UNIT 2 3.8-4
r-LIMITING CONDITIONS FOR OPERATION 3.9 RADI0 ACTIVE WASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING 3.9.1 Two independent Spent Fuel Storage Pool "A" water level monitoring instruments shall be OPERABLE.
APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".
ACTION:
a.
With only one Spent Fuel Storage Pool "A" water level monitoring instrument OPERABLE, immediately verify that the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore a second instrument to OPERABLE status within 7 days.
b.
Hith no Spent Fuel Storage Pool "A" water level monitoring instruments OPERABLE, terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and all operations involving changes in Spent Fuel Storage Pool "A" water inventory and restore at least one instrument to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SPENT FUEL STORAGE FOOL "A" HATER LEVEL 3.9.2 The water level in Spent Fuel Storage Fuel "A" shall be maintained as specified in Section 4.9.2 of the Recovery Operations Plan.
APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".
ACTION:
Hith Spent Fuel Storage "A" water level not in accordance with approved procedures, terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and restore the water level to within specification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
FUEL TRANSFER CANAL (DEEP END) HATER LEVEL MONITORING 3.9.3 Two independent Fuel Transfer Canal (deep end) water level monitoring instruments shall be OPERABLE.
APPLICABILITY: Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (deep end).
ACTION:
a.
Hith only one Fuel Transfer Canal (deep end) water level monitoring instrument OPERABLE, immediately verify that the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore a second instrument to OPERABLE status within 7 days.
THREE MILE ISLAND - UNIT 2 3.9-1
LIMITIE counITION9 FOR OPERATION b.
With no Fuel Transfer Canal (deep end) water level instruments OPERABLE, terminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and all operations involving changes in the Fuel Transfer Canal (deep end) water inventory and restore one inoperable instrument to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
FUEL TRANSFER CANAL (DEEP END) HATER LEVEL 3.9.4 The water level in the Fuel Transfer Canal (deep end) shall be maintained as specified in Section 4.9.4 of the Recovery Operations Plan.
APPLICABILITY: Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (deep end).
ACTION:
With the Fuel Transfer Canal (deep end) water level not in accordance with approved procedures, terminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or s
all activities involving the plenum assembly and restore the water level to within specifications within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
M L HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with exhaust ventilation flow through the HEPA filters during system operation. The Fuel Handling Bu11 ding Air Cleanup Exhaust System is OPERABLE when two of the four system air cleanup exhaust fans are OPERABLE.
APPLICABILITY:
RECOVERY MODE ACTION:
a.
With the Fuel Handling Building Air Cleanup Exhaust System inoperable due to flow requirements, return the flow to within acceptable limits within four (4) hours or; b.
With the Fuel Handling Building Air Cleanup Exhaust System inoperable (other than as allowed in Paragraph 3.9.12.1.a above), suspend all operations involving movement of 11guld and gaseous radioactive wastes in the Fuel Handling Building (other than' sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN) until the system is restored to OPERABLE status.
THREE MILE ISLAND - UNIT 2 3.9-2
RASEE 3/4.4.1 REACTOR COOLANT LOOPS DELETED.
3/4.4.2 REACTOR VESSEL HATER LEVEL MONITORING The Reactor Vessel Water Level Monitor ensures that indication is available to monitor for changes in reactor vessel water level.
This device will provide warning of a leak from the Reactor Coolant System or unexplained increases in Reactor Coolant System inventory which could result in a boron dilution event. Two independent monitors are required to provide redundancy and to minimize the necessity to discontinue processing because of instrument failures.
3/4.4.3 SAFETY VALVES Deleted.
3/4.4.9 PRESSURE / TEMPERATURE LIMIT The Reactor Coolant System pressure and temperature will be controlled in accordance with approved procedures to prevent a nonductile failure of the Reactor Coolant System while at the same time preventing precipitation of the boron used to maintain subcriticality.
During the RECOVERY MCOE, the Reactor Coolant System boundary will be modified periodically to meet recovery objectives. Whenever the Reactor Coolant System is not vented (open to the atmosphere), overpressure protection will be provided to ensure that the allowable RCS pressure is not exceeded.
Reactor coolant chemistry surveillance requirements are included in the RECOVERY OPERATIONS PLAN.
These requirements provide assurance that localized corrosion or pitting in crevice areas, which could tend to promote stress corrosion cracking in heat affected zones of welds in stainless steel piping or components, will not occur.
THREE MILE ISLAND - UNIT 2 B 3/4 4-1
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
LICENSE RECOVERY MODE CATEGORY SOL 1*
OL 1
Non-Licensed 2
- Shift crew composition may be less than the minimum require-ments for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
- During CORE ALTERATIONS an additional SOL or an SOL limited to fuel handling will be stationed on the operating floor, in the command center, or in the control room to directly control the particular CORE ALTERATION activity being perform'ed.
THREE MILE ISLAND - UNIT 2 6-2
ADMINISTRATIVE CONTROLS 6.8.2.1 Each procedure and any change to any procedure prepared pursuant to 6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.
6Property "ANSI code" (as page type) with input value "ANSI 18.7 - 1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..8.2.2 Procedures of 6.8.1.a and changes thereto which alter the distribution or processing of a quantity of radioactive material the release of which could cause the magnitude of radiological releases to exceed 10 CFR 50 Appendix I limits shall be subject to approval by the NRC prior to implementation.
6.8.3.1 Temporary changes to procedures of 6.8.1 may be made provided that; a.
The intent of the original procedure control is not altered, and b.
1)
For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License.
If one of the two above signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of that supervisory person within the department will also be required, or
- 2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization.
If one of the two above signatures is not by a section manager / director within the Department having cognizance of the procedure being changed, the signature of that section manager / director i
within the department will also be required, and c.
The change is documented, Independent Safety Review completed, and the required reviews and approvals are obtained within 14 days, and d.
Those changes to procedures described by 6.8.2.2 are submitted to the NRC for review within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following approval by the management level specified for implementation by Section 6.5.1.9.
6.9 REPORTING REQUIREMENTS 1
ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC i
Region I Administrator unless otherwise noted.
t THREE MILE ISLAND - UNIT 2 6-11
~
SURVEILLANCE RFfilIREMENTS FIRE DETECTION 4.3.3.8.1 Each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
4.3.3.8.2 The NFPA Code 71 supervised circuits supervision associated with the detector alarms of each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
4.3.3.8.3 The nonsupervised circuits between the local panels in Surveillance Requirements 4.3.3.8.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.
4.3.3.8.4 In lieu of Specification 4.3.3.8.2, fire detection instrument for the Southeast Storage Facility shall have circuitry per site-approved procedures.
TilREE MILE ISLAND - UNIT 2 4.3-12
tuRVEILLANCE REQUIREMENTS 4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 4.4.1 Deleted.
REACTOR VESSEL WATER LEVEL MONITORING 4.4.2 The Reactor Vessel Water Level Monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.
SAFETY VALVES 4.4.3 Deleted.
4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 4.4.9.1.1 Deleted.
4.4.9.1.2 Deleted.
4.4.9.1.3 Deleted.
4.4.1.9.4 The pH of the reactor coolant shall be determined to be greater than or equal to 7.5 and less than 8.4 at least once per 7 days.
4.4.1.9.5 The chloride concentration in the reactor coolant shall be determined to be less than or equal to 5 ppm at least once 7 days.
THREE MILE ISLAND - UNIT 2 4.4-1
EllRVEILLANCE RFollIREMENTS 4.9 LIQUID RADNASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING 4.9.1 The Spent Fuel Storage Pool "A" water level monitoring instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.
4.9.2 Verify by surveillance that the water level of Spent Fuel Storage Pool "A".ls between elevations 326'10" and 328'01".
FUEL TRANSFER CANAL WATER LEVEL MONITORING 4.9.3 The Fuel Transfer Canal (deep end) water level monitoring instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.
4.9.4 Verify by surveillance that the water level of the Fuel Transfer Canal (deep end) is between elevations 326'10" and 328'01".
FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 4.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that the Air Cleanup Exhaust System in the normal operating mode meets the following conditions:
1.
Exhaust Flow Rate: With two filter trains and two exhaust fans in operation in the Fuel Handling Building flow rate shall be within the 36,000 cfm to 54,000 cfm operating band.
2.
Filter Pressure Drop: While operating within the flow rate specified in 4.9.12.1.a.1 above, the d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches water gauge.
3.
Fuel Handling Building Pressure: Demonstrate that the syst"em is capable of achieving a negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric.
It may be necessary to close doors and other building openings to achieve the required value.
- Hith the fuel transfer tubes open and the Fuel Pool not flooded in accordance with NRC approved procedures, the FHB exhaust flowrate shall be maintained between 26,000 cfm and 54,000 cfm.
This condition applies only during system operation (not during system surveillance testing) performed to the criteria of Tech. Spec. 4.9.12.1.a THREE MILE ISLAND - UNIT 2 4.9-1