ML20034B981
| ML20034B981 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/24/1990 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20034B961 | List: |
| References | |
| GL-90-02, GL-90-2, NUDOCS 9005010261 | |
| Download: ML20034B981 (3) | |
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't 5.3 REACTOR-Applicability-Applies to the design features of the~ reactor core and reactor coolant system.
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Objective To define the significant design features of the reactor core and-reactor coolant system.
Specification 5.3.1 REACTOR CORE
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5.3.1.1 The reactor core is composed of slightly enriched uranium i
dioxide pellets contained in fuel' rods.
A fuel assembly contains 208 fuel rods arranged in a 15 by 15 lattice,
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' except that substitution of Zircaloy - 4 or stainless: steel filler rods for. fuel rods may= be made in fuel assemblies if justified by cycle-specific reload analyses using an NRC-approved methodology consistent with Technical.
Specification Section 6.9.5.2.
The details. of the fuel assembly. design are described inlTMI-1 FSAR Chapter 3.")
5.3.1.2 The reactor core shall approximate a right circular cylinder with an equivalent diameter;of 128.9 inches. The active fuel height is defined in TMI-1 FSAR-Chapter 3 3")
t 5.3.1.3 The core average and individual batch enrichments for the present cycle are described in TMI-1 FSAR Chapter 3.(*)
5.3.1.4 The control rod assemblies (CRA) and axial power shaping rod assemblies (APSRA) are distributed:in the reactor core as shown in TMI-1 FSAR Chapter 3.(")
The CRA and-APSRA-design data are also described in the FSAR.
5.3.1.5 The TMI-1 core may contain burnable poison rod assemblies (BPRA) as described in TMI-1 FSAR Chapter 3.(*)
5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the FSAR and shall not exceed an enrichment of 4.3 weight percent of US**
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5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 The reactor coolant system shall be designed-and constructed in accordance with code requirements.(*)
5.3.2.2 The reactor coolant system and-any connected auxiliary systems exposed to the reactor coolant conditions of temperature and pressure, shall be designed for a pressure 4
of 2,500 psig and a temperature of 650 F. -The pressurizer and pressurizer surge line shall be designed for a tempera-ture of 670 F.(5) 5-4 Amendment No. 126, 142, 150 9005010261 900424 DR ADOCK 0500 9
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rep 0RTINGRE00lREMENTS 6.9 In addition to the applicable reporting: requirements of Title 10, j
Code of Federal Regulations, the.following identified reports shall' be submitted to the Administrator of the NRC Region 1 Office unless otherwise noted.
6.9.1 Routihe Reports i
A. Startup Report. A summary report of-plant startup andi power escalation testing shall be submitted following--
(1) receipt of an. operating license,.(2) amendment to l
the license involving a. planned: increase'in power level, (3) installation of fuel--that has a different design _or has been manufactured by_a different fuel.
supplier, and (4) modifications-that may-have'signi-
'ficantly altered the-nuclear, thermal, or hydraulic t
performance of the plant. The report shall address-each of the tests identified'in the FSAR and'shall in general include a description of the' measured. values of the operating conditions or characteristics 1
obtained during the test program and a comparison-of
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these values with' design predictions:and specifications.
Any corrective actions that were required to obtain-satisfactory operation shall:also be described.
Any additional specific details required in license conditions based on. other commitments shall be -included -
J in this report.
Startup reports shall be submitted-within- (1) 90 days -
l following cospletion of the startup test program', (2) 90 days following' resumption'or' commencement of commercial l
power operation, or'(3) 9 months"following initial' L
criticality, whichever is earliest.
If the Startup-H Report dcas not cover all three events.(i.e., initial L
criticality, completion of startup test program, and resumption or commencement of commercial-power operation),
supplementary reports shall be submitted at.least:every I
three months until all three events have been completed.
A special report shall be submitted to the Commission within 30 daysLafter cycle startup describing the number of fuel _ rods replaced with filler -rods, should'more than 30 rods in the core, 'or 10 rods in _.any assembly, _ be, replaced
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L per refueling. This special-report shall 'be submitted to l
the Regional Administrator of the Regional Office of the l
NRC.
B. Annual Reports. Annual reports covering.the activities of the unit as described.below during the previous calendar-year shall be submitted. prior to March 1 of each year.
(A-single submittal may~be made for. the. station. The sub-mittal should combine those sections that are common to both units at the station.)
i 6-12 Amendment No. 12, 37, 77
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A. tabulation on: an' annual basis of the-number of-i station, utility, and other personnel:(including' contractors) receiving' exposures: greater than 100 mrem /yr'and their associated man-rem exposure' according to work and -job functions,; (e.g', reactor-operations and surveillance, inservice inspection, 4
routine maintenance, special maintenance-(describe maintenance), waste processing; and refueling).,.The-dese' assignment to various duty functions may be estimates based on pocket dosimeter, TLD,' or film badge measurements. 1Small exposures totaling less.
than 20% of the individual tctal dose need not be.
accounted for.< In the-aggregate,: at least 80% of the
-total whole. body dose'receivedtfromiexternal~ sources-shall be assigned to specific major work-functions'.
-(This tabulation supplements the requirements of Section 20.407Dof 10 CFR part 20;)*
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