ML20065S597
| ML20065S597 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/11/1990 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20065S592 | List: |
| References | |
| NUDOCS 9012210205 | |
| Download: ML20065S597 (9) | |
Text
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ENCLOSURE PROPOSED TECllNICAL SPECIFICATION AND RESPECTIVE SAFETY ANALYSES' IN Tile MATTER OF AMENDING LICENSE NOS. DPR-51 AND NPF-6
- ENTERGY OPERATIONS, INCORPORATED ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 DOCKETS NOS 50-313 AND 50-368 9012210205 901211 hDh ADOCK 05000313 PDR
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PROPOSED CHANGE The proposed change to ANO-1 Technical Specification (TS); deletes Item 6.9 1 and Section 6.13 relating to Environmental _ Qualifications. The chango to ANO-2 TS dolotes-Item 6.10 m and Section 6.12 relating to -
Environmental Quallfications.
- )
BACKGROUND By letter dated October 124,1980,- the staf f issued an orderLthe subject of which was " Order for Modification of License Concerning Environmental-Qualification of Safety-Rolated Electrical Equipment.". ~ In this Order the License for Arkansas Nuclear one was-modified to include Environmental ji Qualifications as part of Section 6 Administrative Controls ofE he t
Technical Specifications.~ Since that time Environmental Qualifications _has-
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boon included in the Codo of Federal Regulations Las 10CFR50.49,
" Environmental Qualification of Electrical-Equipment 1Important to Safety.
j for Nuclear Power Plants."
DISCUSSION
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.i On June 30, 1982 the commission issued. interim'fina1Lrule 10CFR50.49.
As 10CFR50.49 supersedos the October 24, 1980 Order, Ectorgy-proposes' tot
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remove the reference to-the October 24, 1980 Order-from the TS as an1 Administrative Change.- The deadlino imposed {by the Order has been :
superceded by 10CFR50.49 section g.
Tho' requirement:for complete and-auditable records to be maintained in'a contral location has t'on-superceded by_10CFR50.49'section J.
This change is being=mado to simplify ~
the TS by removing an unnecessary specification.which has been superceeded by another regulatory requirement.
DETERMINATION OF SIGNIFICA8T HAZARDS t
An ovaluation of-the proposed change has.been performed in accordancolwith 10CFR50.91(a)(1)-regarding no significant-hazards consideration using the
~
standards in 10CFR50.92(c). LA discussion of;those standards;as they relate j
_to this;amondment-request follows;-
griterion 1. - Does not involve a significant -increase in::th'o= probability,
or. consequences of an _ accident previously (ovaluated.
L As the Environmental Qualificatjons ofocquipment.is: Included j
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in the Code of Federal Regulations this: constitutes'an' Administrativo Change and thereforo doos = not 'involvoia' significantJincreaso,in the probabilityEor-consequences of i
- an-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.-
No new or different kind of accident from any previously evaluated is created as this is an Administrative Change.
The Environmental Qualifications of equipment is required by.
the Code of Federal Regulations, 10CFR50.49.
Criterion 3 - Does not involve a significant reduction in the Margin of Safety.
No reductlon in the Margin of Safety is incurred as Environmentel Qualifications of equipment is require by 10CFR50.49. This supersedes the October 24, 1980 Order.
The Cuomission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration j
exisca.. The proposed amendment most closely matches examples.
j
)
(1)
"A purely administrative change to Technical Specification: for example, a change to achieve consistency throughout the Technical Specifications, correction of an error or a change in nomenclature."
and (vil)"A change to conform a license to changes in the regulations, where 1
the license change results.in very minor. changes to-facility operations clearly in keeping with the regulations."
Based on the above evaluation it is concluded that the proposed Technical l
Specification change does not constitute a significant hazards concern.-
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PROPOSED TECilNICAL-SPECIFICATION CIIANGES ANO-UNIT'i 4
a
-_ --=__
J
1 h.
Records of in-service inspections performed pursuant to
-these Technical Specifications.
l i.
Records of Quality Assurance activities. required = by Section-17'of the Quality. Assurance Manual'for' Operations.
j.
Records'of reviews performed for changes made to procedures-or equipment or reviews of tests _and' experiments _ pursuant to 10CFR50.59.
k.-
Records o_f meetings of the1PSC and the SRC.
1.
(DELETED) m.
Records of.the, service-lives-of the seals of all-hydraulic snubbers-applicable-to Specification 3.16Lincluding the date-j
.at which the service. life commences,and associated 1
installation and maintenance records.
a n.
. Records of analyses required-by the Radiological-i Environmental Monitoring Program.
a 6.10 RADIATION PROTECTION PROGRAM
' Procedures for personnel radiation protection shall be prepared consistent
- with the requirements of 10CFR-Part 20 and shall. be approved, maintained ~
and adhered to for all operations involving personnel radiation. exposure.
6.11 HIGH RADIATION AREA g
6.11.1 In lieu of the." control device" or " alarm signal"_ required by ;
paragraph 20.203(c)(2) of 10CFR20, each high radiation; area (as defined in-20.202(b)(3) of 10CFR20) in which the-' intensity of; radiation 11s 1000:
mrem /hr or-less. shall be barricaded and conspicuously posthd:asj a high-radiation: area and shall be controlled byJrequiring the' issuance of a -._
radiation work permit.
Any individual or group ofaindividualsjpermitted to 3
enter such areas shall.be provided with or accompanied by: one Lor'more of 1
the.following:
i La.
A' radiation monitoring device which continuously, indicates the radiation' dose: rate in the area, h
b.
A radiation monito' ring _ device which' continuously' integrates the radiation dose rate in the area and alarms when!a pre-set 3
integrated dose is: received.
JEntry into suchEareas with-this-monitoring ' device 'may be:made <af ter-the dose ~ rate levelT in the
' area has been established and; personnel-have been:made;
' knowledgeable-ofcthem.
1 c.
An individual qualified in radiation protection procedures who is.
J
. equipped with-a radiation dose' rate' monitoring devicei:This individual shall be responsible.for providing positive control over the activities within the area and shall-perform periodic
'i radiation surveillance at the frequency specified in the radiation work permi_t.
i 129
, Amendment No. 26, 34,-53, 10/24/80-erder-64, 84, 88, 200 h l
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6.13 (DELETED)-
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. Amendment No.
147
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PROPOSED TECHNICAL SPECIFICATION CHANGES ANO-UNIT 2 t
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ADMINISTRATIVE CONTROL f.
Records of reactor tests and experiments, g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to those Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of taats and experiments pursuant to 10CFR50.59.
I k.
Records of meetings of the PSC and the SRC.
1.
Records of changes to the Core Protection Calculator System (CPCS) SOFTWARE.
Changes to the CPCS SOFTWARE shall be made in accordance with methods approved by the NRC. These records shall include the following:
1.-
Purpose of change.
2.
Detailed description of changes including algorithms, changes to the assembly listings, checksums and disk identification numbers.
3.
Summary of validation test results.
m.
(DELETED)
-l n.
Records of the service lives of the. seals of all hydraulic snubbers required by Specification 3.7.8, including the date at which the service life commences and associated installation and maintenance records.
-6.11 RADlATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall-be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (DELETED) l ARKANSAS-UNIT 2 6-23 Amendment No. 72 l
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n ADMINISTRATIVE CONTROL-6.12.2
' DELETED) l 6.13 HIGH RADIATION AREA 6.13.1 In lieu of tho'"contro1' device"'or " alarm signal" required by paragraph 20.203(c)(2) of.10 JFR 20, each high radiation area (as. defined in 20.202(b)(3) of.10 CFR 20)-in which the intensity of. radiation is_1000 I
mrom/hr or less shall be barricaded and conspicuously. posted as a high radiation area-and entrance thereto shall be controlled by requiring the issuance of a radiation' work permit. -Any-individual-or group of individuals' permitted to_ enter such areas shall:be provided-with-or, accompanied by one-or more of the followingt H
a.
A radiation monitoring-device which continuously indicates the radiation dose:rste in:the area, b.
A radiation monitoring device _which continuously integrates the radiation dose rate in:the area and-alarms when a preset'.
integrated dose is received.- Entry into.such areas with this monitoring device may be mad _o after the dose rate: level in.tho'-
area has been established and personnel have been-mado-knowledgeable of them.-
c.
- An individual qualified in radiation _ protection procedures who is-equipped with a radiation-dose' rate. monitoring device.. This-__
-i individual shall. be responsible-for providing positive control'
--over the activities;within theLarea and.shn11' perform periodic'-
radiation surveillance at the: frequency speciflediin the_
radiation work permit.
-6.13.2' The requirements of 6.13.1, above, shall'also-apply-to each high-radiation area in which the intensity of radiation is greater than 1000 mrom/hr.
In addition, locked-doors'sha11:be provided,to prevent unauthorized entry into such areas!a' nd access to those areas shall be
, maintained under the. administrative control of the Shift Shpervisor on duty and/or the designated radiation ' protection manager.
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ARKANSAS-UNIT 2 6-24 pffff fffff OfffEff 25,'Jy$$
, Amendment No. 2/, 2), 49, pp, pf, l
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