ML20216J112
| ML20216J112 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/25/1987 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 8707020124 | |
| Download: ML20216J112 (6) | |
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June 25,1987 Docket No. 50-320 Mr. F.R. Standerfer Vice President / Director Three Mile Island Unit 2 GPU Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 17057
Dear Mr. Standerfer:
SUBJECT:
REC 0VERY OPERATIONS PLAN CHANGE REQUEST 40 By letter dated January 27, 1987 you submitted Technical Specification Change Request (TSCR) No. 55 and Recovery Operations Plan Change Request (ROPCR) No.
- 40. The TSCR and R0PCR proposes to modify the TMI-2 license and surveillance requirements by redefining the scope of licensee procedures and changes thereto i
that require NRC staff approval. Only those procedures which alter the distribu-tion or processing of a quantity of radioactive material, the release of which could cause the magnitude of radiological releases to exceed the design objec-tives of 10 CFR 50 Appendix I, would require NRC approval prior to implemen-tation.
We have completed our review of the proposed Technical Specification changes and issued our approval of those changes with the stiff's supporting safety evalua-tion in separate correspondence. That safety evaluation also provides the basis for our approval of the proposed R0PCR 40, which modify those sections of the Recovery Operations Plan corresponding to the approved Technical Specification changes. The revised Recovery Operations Plan pages are enclosed. Our approval l
of your R0PCR No. 40 is designated as change approval No. 37. These changes are effective as of the date of this letter.
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99hekh bW2y William D. Travers, Director TMI-2 Cleanup Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc w/ enclosures:
See next page TA/PD42t4d D/PD42M MMasnik/vh WTravers 6/2f/87 6/25/87
- 07 0 0
Enclosure s
DOCKET NO. 50-320 Replace the following pages of the TMI-2 Recovery Operations Plan with the i
enclosed pages as indicated:
4.3-12 4.4-1 4.9-1 4
SURVEILLANCE REQUIREMENTS 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 tne Southeast Storage Facility shall have circuitry' per site-approved procedures.
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1 THREE MILE ISLAND - UNIT 2 4.3-12 Change No. 37 i
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SURVEILLANCE REQUIREMENTS 4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 4.4.1 Deleted.
4.4.2 REACTOR VESSEL WATER LEVEL MONITORING 4.4.2 The Reactor Vessel Water Level Monitoring Instrumentation shall be demonstrated CPERABLE as required by Table 4.3-7.
SAFETY VALVES i
4.4.3 Deleted, 4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM
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4.4.9.1.1 Deleted.
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4.4.9.1.2 Deleted.
4.4.9.1.3 Deleted.
4.4.9.1.4 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.
4.4.9.1.5 The chloride concentration in the reactor coolant shall be deter-mined to be less than or equal to 5 ppm at least once per 7 days.
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THREE MILE ISLAND - UNIT 2 4.4-1 Change No. 37
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SURVEILLANCE REQUIREMENTS 4.9 LIQUID RADWASTE 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 0PERABLE as required by Table 4.3-7.
4.9.2 Verify by surveillance that the water level of Spent Fuel Storage Pool "A" is 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 conaitions:
1.
Deleted.
2.
Filter Pressure Drop:
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 system 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 build-ing openings to achieve the required value.
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THREE MILE ISLAND - UNIT 2 4.9-1 Change No. 37
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. 'o DISTRIBUTION Docket File 50-320 NRC PDR.
t Local PRD TMI-2 HQ, file THI-2 Site Rdg. File F. Schroeder AD/ Region I W.. Travers M. Masnik OGC/LChandler S. Lewis D. Hagen E. Jordan J. Partlow ACRS(10) cc: Plant Service List T. E. Demitt -
R. E. Rogan S. Levin W. H. Linton
~A. W. Miller J. J. Byrne I
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