2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS
| ML20117G750 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/23/1996 |
| From: | Dewease J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117G753 | List: |
| References | |
| RTR-NUREG-1432 2CAN089609, 2CAN89609, NUDOCS 9609050312 | |
| Download: ML20117G750 (12) | |
Text
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Cnt:rgy Operation?,lnc.
P.O Box 31995
= ENTERGY aackeo, es 3928c-1995 Tel 601368 5760 Fax 601368 5768 Jerrold G. Dewease vce Pmsant overetws S<suwt August 23,1996 2CAN089609 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555 i
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Conversion Of The Design Features Section Of The Technical Specifications j
To The Improved Standard Technical Specifications Gentlemen:
Attached for your review and approval is a proposed amendment to Arkansas Nuclear One Unit 2 (ANO-2) Technical Specifications (TS). The proposed amendment revises Section 5.0, Design Features, and would for the most part, adopt NUREG-1432 Revision 1, improved
" Standard Technical Specifications for Combustion Engineering Plants" (ISTS) for this j
section of the TS. ANO-2 has previously committed to implementation of the ISTS. This
-i amendment request is being submitted as a TS line item improvement similar to that which the NRC has previously approved for the Calvert Cliffs, Davis-Besse, and Palo Verde Nuclear Generating Stations.
The proposed change has been evaluated in accordance with 10CFR50.91(a)(1) using criteria in 10CFR50.92(c) and it has been determined that this change involves no significant hazards considerations. The bases for these determinations are included in the attached submittal.
Entergy Operations requests that the effective date for this change be within 30 days of issuance. Although this request is neither exigent nor emergency, your prompt review is requested prior to the next ANO-2 refueling outage (2R12) which is currently scheduled to J
begin April 11,1997.
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9609050312 960823 PDR ADOCK 05000360 p
U. S. NRC August 23,1996 2CAN089609 Page 2 Very truly yours, i
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D/rde Attachments To the best of my knowledge and belief, the statements contained in this submittal are true.
SUBSCRIBED AND SWORN TO before me, a Notary Public in and for h County and the State of Mississippi, this cht1 day of b e,uiT
,1996.
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U. S. NRC August 23,1996
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2CAN089609 Page 3 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 j
l-Arlington, TX 76011-8064 i
l NRC Senior Resident Inspector l
Arkansas Nuclear One P.O. Box 310 London, AR 72847 a
l Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 j
One White Flint North i
l1555 Rockville Pike i
Rockville, MD 20852
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i Mr. Bernard Bevill Acting Director, Division of Radiation Control and Emergency Management l
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4815 West Markham Street Little Rock, AR 72205 i
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i ATTACHMENT
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I IQ 2CAN089609 PROPOSED TECHNICAL SPECIFICATION AND RESPECTIVE SAFETY ANALYSES i
IN THE MATTER OF AMENDING a
i LICENSE NO. NPF-6
'I ENTERGY OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNIT TWO DOCKET NO. 50-368
I tm e-Attachment to 2CAN089609 j
Page 1 of 7 l
DESCRIPTION OF PROPOSED CHANGES The proposed amendment revises the Section 5.0 of the Technical Specifications (TS), Design Features, and would for the most part, adopt NUREG-1432 Revision 1, improved " Standard Technical Specifications Combustion Engineering Plants" (ISTS) for this section of the TS.
ANO-2 has previously committed to implementation of the ISTS (0CAN069502) with the Unit 1 project currently well under way. The proposed amendment will also allow the relocation of portions of the design features section of the TS to other licensee controlled documents. The relocated sections will retain the appropriate regulatory controls under 10 CFR 50.59 to assure continued protection of the public health and safety.
The proposed amendment request removes the information in the following design features sections from the TS because it is either contained in, or will be added to, licensee controlled documents when this amendment request is approved and will be controlled by the requirements of 10 CFR 50.59. The information has been removed from the following sections: 5.1.1 and the corresponding Figure 5.1-1; 5.1.2 and the corresponding Figure 5.1-2; 5.2.1; Figure 5.1-3; 5.2.2; podions of 5.3.1, 5.4.1, 5.4.2, 5.5.1,and 5.7.1 with the associated Table 5.7-1.
TS 6.8.4 and 6.8.4.a were added to establish a Component Cyclic or Transient Limit program.
TS 6.10.2.e was modified to ensure the records are maintained for the Component Cyclic or Transient Limit program for the duration of the operating license.
TS 3.11.2.1, 3.11.2.2, 3.11.2.3, 3.11.2.4, and 3.11.2.5 were modified to refer to the Offsite Dose Calculation Manual (ODCM) Figure 4-2 due to Figure 5.1-3 being removed from the TS.
The index page XV was modified to reflect the changes to Section 5.0 titles and page numbers.
BACKGROUND The content required of the TS is set forth in 10 CFR 50.36. The regulation requires that the TS include items in the following five specific categories: (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. Specifically, 10 CFR 50.36(c)(4) states, in pan, " Design features to be included are those features of the facility such as the materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section."
The proposed amendment revises Section 5.0 of the TS and would for the most pan, adopt the ISTS for the Design Features and section 6.8.4.a, while complying with 10 CFR 50.36(c)(4).
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i Attachment to 2CAN089609 o
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DISCUSSION OF CHANGE i
The proposed amendment revises the design features section of the TS and would for the most part, adopt the ISTS for this section of the TS. ANO-2 has previously committed to implementation of the ISTS. The proposed change will allow the relocation of portions of the design features section to other licensee controlled documents in accordance with the ISTS.
The relocated sections will retain the appropriate level of regulatory authority and control.
The specific changes are as follows:
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Index page XV was changed to reflect the changes to the design features section titles and j
page numbers.
i TS 3.11.2.1, 3.11.2.2, 3.11.2.3, 3.11.2.4, and 3.11.2.5 were modified to refer to the Offsite Dose Calculation Manual (ODCM) Figure 4-2 due to Figure 5.1-3 being removed from the i
TS. Figure 5.1-3 has been added to the ODCM as Figure 4-2. Removal of this figure is j
consistent with the ISTS format. In action "b." in the above TS, the word specifications was l
reduced to its singular form.
1 Section 5.1.1: Section 5.1.1 and the corresponding Figure 5.1-1 are being removed from the i
TS. This is consistent with the ISTS. Figure 5.1-1 is shown in the Safety Analysis Report (SAR) as Figure 2.1-2. The exclusion area definition has been included as the last sentence in Section 5.1 of the proposed change.
Section 5.1.2: The low population zone section 5.1.2 and the corresponding Figure 5.1-2 are being removed from the TS. This is consistent with the ISTS. A description of the low population zone is included in section 2.1.3.3 of the SAR.
Section 5.2.1: This containment design features section has been removed from the TS. The design features that were located in this section are either duplicated in or will be added to the SAR. The following sections of the SAR contain similar containment design requirements; section 12.1.2.5, Table 6.2-7, Table 1.3-1, Figure 1.2-5, Figure 3.8-1, Figure 3.8-2, Figure 3.8-5, Figure 3.8-7, and Figure 3.8-8.
The minimum containment sump thickness will be added to the SAR. Modifications or alterations to the design features as described in the SAR are controlled under the 10 CFR 50.59 review process.
Section 5.2.2: This section has been removed from.the TS. The design pressure and temperature for the containment building is located in the basis for TS 3/4.6.1.4 and on SAR Table 6.2-7. Modifications or alterations to these documents are controlled under the 10 CFR 50.59 review process.
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s Attochment to 2CAN089609 l
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l Section 5.3.1: The reactor core fuel assembly section has been removed from the TS and replaced with proposed section 5.2.1.
The enrichment information from this section is i
satisfied by TS 3.9.12. The limit of 2114 grams of uranium for each fuel rod will be added to i
the SAR. The remaining information that was in this section is either duplicated in the proposed section 5.2.1 or listed in the SAR in section 4.1, 4.2.1.2.3 or in SAR Table 4.2-1 and is therefore adequately controlled under the 10 CFR 50.59 review process.-
Section 5.3.2: The control element assemblies section has been moved to proposed section 5.2.2.
Section 5.4.1: The Reactor Coolant System (RCS) design pressure and temperature section has been removed from the TS in accordance with the ISTS. This design information is
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depicted in the SAR section 5.2 and in Table 5.1-1. TSs 3.2.6, 3.2.8, and 3/4.4 adequately control the RCS parameters such as temperature, pressure, and boundary degradation. These requirements are maintained tader the TS amendment proi ess or the 10 CFR 50.59 process and are therefore adequately controlled.
I Section 5.4.2: The RCS design volume section has been removed from the TS in accordance i
with the ISTS. This design information is depicted in the SAR on Tables 5.1-1, 5.3-2, 5.5-2, 5.5-4, 5.5-6 and 6.2-8 and is therefore adequately controlled under the 10 CFR 50.59 review i
process. The only pertinent information that is not included in the proposed section is the volume tolerance that will be included in the SAR.
l Section 5.5.1: The Meteorological Tower Location section and the associated Figure 5.1-1 j
are being removed from the TS in accordance with the ISTS. The SAR section 2.3.3.1.1 describes the meteorological tower and its location. The meteorological tower is also shown on SAR Figure 2.1-3 and is therefore adequately controlled under the 10 CFR 50.59 review process.
l Section 5.6.1.1: The Spent Fuel Storage Criticality section has been revised to the ISTS format as proposed in section 5.3.1 with all the pertinent information retained.
Section 5.6.1.2: The New Fuel Storage Criticality section has been revised to the ISTS i
format as proposed in section 5.3.2. The allowance for uncertainties will be added to the SAR.
I Section 5.6.2: The Fuel Storage Drainage section has been moved to proposed section 5.3.3.
Section 5.6.3: The Fuel Storage Capacity section has been moved to proposed section 5.3.4.
i Section 5.7.1: The Component Cyclic or Transient Limits section along with the associated Table 5.7-1 have been removed from the TS in accordance with the ISTS. The RCS design transients are described in section 5.2.1.5 of the SAR. The TS cyclic or transient limits that are currently not in the SAR will be added.
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Attachment to 2CAN08%09 Page 4 of 7 Section 6.8.4 and 6.8.4.a were added to establish a Component Cyclic or Transient Limit program. This program is in accordance with the ISTS.
Section 6.10.2.e: The record retention requirements for the transient or operational cycles have been maintained by removing the reference to Table 5.7-1 and inserting a reference to l
the Component Cyclic or Transient Limit program. The record retention requirements will be i
placed in the SAR.
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The following design features sections have been added to the TS in accordance with the ISTS:
Proposed Section 5.1: The site location description was added along with a description of the area defined as the exclusion area. The text description of the site location is consistent with l
the ISTS format. The description of the exclusion area was taken from Figure 5.1-3.
Proposed Section 5.2.1: The description of the reactor core fuel assemblies is consistent with the ISTS. The site specific number of fuel assemblies was previously listed in section 5.3.1.
The option of using ZIRLO clad fuel rods in addition to the zircaloy clad fuel rods was'added in accordance with the ISTS. ZIRLO is a zirconium based alloy that has been previously accepted by the NRC in 10 CFR 50.44 and would facilitate its future potential use by ANO-2.
The current fuel cladding is described as zircaloy-4 in SAR section 4.2.1.2 and would therefore require a SAR change and 10 CFR 50.59 evaluation to allow the use of the ZIRLO cladding. In addition, the proposed section 5.2.1 requirement, " Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases" will ensure future use of the ZIRLO cladding will not have an adverse effect on safety.
The last sentence was added to proposed section 5.2.1 allowing the use of other cladding material with approved exceptions. This change will allow the use of future cladding materials without requiring a TS amendment.
However, an exemption to the Code of Federal Regulations would be required, ensuring that the NRC has approved the use of other cladding materials. The use of any cladding material other than zircoly-4 would require a SAR change and 10 CFR 50.59 evaluation to allow its use. In addition, the proposed section 5.2.1 requirement that " Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or j
analyses to comply with all fuel safety design bases" will ensure future use of different cladding materials will not have an adverse effect on safety. A similar proposal was approved for Palo Verde Nuclear Generating Station on March 6,1996.
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Attachment to g-2CAN089609 Page 5 of 7 Proposed Section 5.2.2: The Control Element Assemblies section has been transferred from existing TS section 5.3.2 without any changes other than renumbering the section. This section is consistent with ISTS with the exception of the site specific number of CEAs and the discussion of the type of control material in use. The control material is not included in the proposed section 5.2.2 because it was not included as a design features requirement in the current TS. The control material is also discussed in the SAR section 4.2.3.2.2 and is therefore adequately controlled under the 10 CFR 50.59.
l Proposed Section 5.3.1.a: The proposed section 5.3.1.a ensures the enrichment and storage requirements of the ISTS are satisfied without duplicating the requirements of TS 3.9.12 in this section. These requirements will be reviewed to determine which section is appropriate for them to reside in when TS 3.9.12 is converted to the ISTS format.
Proposed Section 5.3.1.b: The proposed section 5.3.1.b is consistent with ISTS.
Proposed Section 5.3.1.c: The proposed section 5.3.1.c is consistent with ISTS with the site specific nominal distance between fuel assemblies in the storage racks. The nominal 9.8 inch center to center distance requirement was extracted from SAR Figure 9.1-12A.
Proposed Section 5.3.2.a: The proposed section 5.3.2.a is consistent with ISTS with the site j
specific maximum enrichment of 4.1 weight percent that is currently required by TS 5.6.1.2.
Proposed Section 5.3.2.b: The proposed section 5.3.2.b is consistent with ISTS.
Proposed Section 5.3.2.c: The proposed section 5.3.2.c is consistent with ISTS.
Proposed Section 5.3.2.d: The proposed section 5.3.2.d is consistent with ISTS with the site specific nominal distance between new fuel assemblies in the storage racks. The 25 inch center to center distance requirement was extracted from TS 5.6.1.2.-
Proposed Section 5.3.3 was previously located in section 5.6.2.
Proposed Section 5.3.4 was previously located in section 5.6.3.
Attachm:nt to 2CAN089609 Page 6 of 7 1
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DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION An evaluation of the proposed change has been performed in accordance with 10 CFR 50.91(a)(1) regarding no significant hazards considerations using the standards in 10 CFR 50.92(c). A discussion of these standards as they relate to this amendment request follows:
Criterion 1 - Does Not Involve a Significant Increase in the Probability or 1
Consequences of an Accident Previously Evaluated.
The proposed amendment revises the Section 5.0, Design Features, and would for the most part, adopt NUREG-1432 Revision 1, " Standard Technical Specifications Combustion Engineering Plants," for this section of the technical specifications. This proposed change will s
also allow the relocation of portions of the design features section of the technical specifications to other licensee controlled documents that are controlled under 10 CFR 50.59.
3 This approach is consistent with the NRC final policy statement and the staffs Technical-i Specification line item improvement program. The relocation of information to licensee controlled documents will improve the usability and readability of technical specifications without changing any of the design requirements for the facility.
i This amendment request does not remove or modify any of the design requirements for the facility or affect any accident initiators, conditions or assumptions for any accident previously evaluated. Therefore, this change does g involve a significant increase in the probability of any accident previously evaluated.
This amendment request is administrative in nature and does not affect any system or 2
component functional requirements. This change does not affect the operation of the plant or i
affect any component that is used to mitigate the consequences of any accident. Therefore, l
this change does m involve a significant increase in the consequences of any accident
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previously evaluated.
l Therefore, this change does g involve a significant increase in the probability or consequences of any accident previously evaluated.
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Criterion 2-Does Not Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated.
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The relocation of existing requirements from the technical specifications to other licensee l
controlled documents and the reformatting of the design features section of the technical specifications to the NUREG-1432 format are changes that are administrative in nature. This j
change does not modify or remove any plant design requirement. The proposed change will not affect any plant system or structure, nor will it affect any system functional or operability requirements. Consequently, no new failure modes are introduced as a result of this change.
Therefore, this change does g create the possibility of a new or different kind of accident from any previously evaluated.
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Attachment to 2CAN089609 Page 7 of 7 Criterion 3 - Does Not Involve a Significant Reduction in the Margin of Safety.
The proposed amendment request represents a relocation of a portion of the information previously located in the technical specification design features section to other licensee controlled documents that are controlled under 10 CFR 50.59, The proposed change is administrative in nature because the design requirements for the facility remain the same. The proposed change does not represent a change in the configuration or operation of the plant.
Therefore, this change does p.qi involve a significant reduction in the margin of safety.
Therefore, based upon the reasoning presented above and the previous discussion of the amendment request, Entergy Operations has determined that the requested change does p_pf involve a significant hazards consideration.
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PROPQSED TECHNICAL SPECIFICATION CHANGES l
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