ML20234B956
| ML20234B956 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/25/1987 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20234B936 | List: |
| References | |
| NUDOCS 8707060288 | |
| Download: ML20234B956 (11) | |
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a GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. DPR-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The applications for amendment dated January 27, 1987 by General Public Utilities Nuclear Corporation (licensee), comply with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 1
10 CFR Chapter I; q
B.
The facility will operate in conformity with the application, the l
I provisions of the Act, and the regulations of the Commission; i
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, arid paragraph 2.C.(2) of Facility Operating License No. DPR-73 is hereby amended to read as follows:
2.0 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 28 are hereby incorporated in the license. The licensee shall operate the facility in 8707060298 870625-PDR ADDCK 05000320 i
P pyg
.g-accordance with Technical Specifications and all Commission Orders issued subsequent to March 28, 1979.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7 ?dd&
William D. Travers, Director TMI-2 Cleanup Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation j
Date of Issuance:.' June 25,' 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 28
_TO FACILITY OPERATING LICENSE N0. DPR-73 DOCKET NO. 50-320 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and j
contain a vertical line indicating the area of change.
Amendment Page 3.1-2 3.4-1 3.8-4 l
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3.9-2 B 3/4 4-1 6-2 6-11 I
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LIMITING CONDITIONS FOR OPERATION BORON CONCENTRATION i
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:
REC 0VERY 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 l
to within acceptable limits.
l 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 maintained between 4350 and 6000 ppm.
APPLICABILITY:
REC 0VERY 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 l
HECHANISMS l
3.1.3.1 deleted.
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l THREE MILE ISLAND - UNIT 2 3.1-2 Amendment No. 28
LIMITING CONDITIONS FOR OPERATI0f4 3.4 REACTOR COOLANT SYSTEM REACTOR C0OLANT LOOPS 3.4.1 Deleted REACTOR VESSEL WATER LEVEL MONITORING l
3.4.2 As a minimum two independent reactor vessel level monitoring instruments shall be OPERABLE.
APPLICABILITY:
REC 0VERY MODE WITH THE RV HEAD REMOVED ACTION With only one reactor vessel level monitoring instrument OPERABLE, terminate a.
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 T,yg 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.
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il THREE MILE ISLAND - UNIT 2 3.4-1 Amendment No. 28
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LIMITING CONDITIONS FOR OPERATION 3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS
- 3. S. 2.1 A.C.
DISTRIBUTION 3.S.2.1.a The A.C. electrical busses listed in Section 4.8.2.1.a 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 l
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 />.
3.8.2.1.b The AC electrical busses listed in Section 4.8.2.1.b of the REC 0VERY OPERATIONS PLAN shall be OPERABLE and energized.
APPLICABILITY:
REC 0VERY MODE ACTION:
a.
With any of the above A.C. busses incapable of being supplied by its respective inverter, restore that capability to the affected bus f
within 7 days.
b.
With any of the above A.C. busses de-enerized, 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 />.
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THREE MILE ISLAND - UNIT 2 3.8-4 Amendment No. 28
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.
1 APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".
ACTION:
With only one Spent Fuel Storage Pool "A" water level monitoring instru-a.
ment 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.
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b.
With no Spent Fuel Storage Pool "A" water level monitoring instruments OPERABLE, terminate all activities involving any Canister containing 1
core material in or over Spent Fuel Storage Pool "A" and all operations I
involving changes in Spent Fuel Storage Pool "A" water inventory and l
4 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 POOL "A" WATER LEVEL i
j 3.9.2 The water level in Spent Fuel Storage Pool "A" shall be maintained as l
l specified in Section 4.9.2 of the Recovery Operations Plan.
l APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".
ACTION:
i With Spent Fuel Storage Pool "A" water level not within the specified band, terminate all activities involving any Canister containing core material in or l
over Spent Fuel Storage Pool "A" and restore the water level to within specifi-cation 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) WATER 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:
With only one Fuel Transfer Canal (deep end) water level monitoring a.
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 Amendment No. 28
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LIMITING CONDITIONS FOR OPERATION i
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) WATER LEVEL 1
3.9.4 The water level in the Fuel Transfer Canal (deep end) shall-be maintained I
at the level specified in Section 4.9.4 of the Recovery Operations Plan.
l APPLICABILITY:
Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (deep end).
ACTION:
a.
With the Fuel Transfer Canal (deep end) water level not within the specified band, terminate all activities involving any Canister contain-ing core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly 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 HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE.
APPLICABILITY:
RECOVERY MODE ACTION:
With the Fuel Handling Building Air Cleanup Exhaust System inoperable, restore the system to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or, suspend all operations involving movement of liquid and gaseous radioactive wastes in the Fuel Handling Building (other than sampling evolutions required by the Technical Specifications or REC 0VERY OPERATIONS PLAN).until the system is restored to OPERABLE status.
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THREE MILE ISLAND - UNIT 2 3.9-2 Amendment No. 28
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I 3/4.4 REACTOR COOLANT SYSTEM i
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3/4.4.1 REACTOR COOLANT LOOPS Deleted.
3/4.4.2 REACTOR VESSEL 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 l
Deleted.
i 3/4.4.9 PRESSURE / TEMPERATURE LIMIT l
The Reactor Coolant System pressure and temperature will be controlled in I
accordance with approved procedures to prevent a nonductile failure of the l
Reactor Coolant System while at the same time preventing precipitation of
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the boron used to maintain subcriticality.
During the REC 0VERY MODE, 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 pro-vided to ensure that the allowable RCS pressure is not exceeded.
Reactor coolant chemistry surveillance requirements are included in the i
l REC 0VERY OPERATIONS PLAN.
These requirements provide assurance that localized l
corrosion or pitting in crevice areas, which could tend to promote stress corrosion cracking in heat affected zonas of welds in stainless steel piping l
or components, will not occur.
i It!REE MILE ISLAND - UNIT 2 B 3/4 4-1 Amendment No. 28
ADMINISTRATIVE CONTROLS Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
LICENSE RECOVERY MODE CATEGORY SOL 1*
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I Non-Licensed 2
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- Shift crew composition may be less than the minimum require-l ments for a period lof 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 i
shift crew composition to within the minimum requirements i
of Table 6.2-1.
- During CORE ALTERATIONS an additional SOL or an 50L limited to i
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 performed.
i THREE MILE ISLAND - UNIT 2 6-2 Amendment No. 28 J
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ADMINISTRATIVE CONTROLS
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i 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 Appen-
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4 dix I design objectives, 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:
The intent of the original procedure control is not altered, and a.
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 i
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 within the department will also be required, and The change is documented, Independent Safety Review completed, and c.
the required reviews and approvals are obtained within 14 days, and l
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 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 Region I Administrator unless otherwise noted.
THREE MILE ISLAND - UNIT 2 6-11 Amendment No. 28
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