ML20246K281

Proposed Tech Specs Re Surveillance Requirements

ML20246K281
Person / Time
Site:	Davis Besse
Issue date:	08/23/1989
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20246K252	List: ML20246K247 ML20246K267 ML20246K281
References
1702, NUDOCS 8909050424
Download: ML20246K281 (4)

Text

- Docket Number 50-346 License Number NPF-3 Serial Number 1702 Attachment 1

- Page 4-APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPER-

. ATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Sur-veillrnce Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval Withf 4 rname dera#c uknWh M 4 ewMf/YN#M of tu 'spec.hed wmuwnucM

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ell ==ble-extension-not to-exceed-251-ef-the-sur-

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b. f. tet:1 mui. cabined-interval-time-for-any-3-consecutive-wes+= nat M evreed-3r25--times-the gecified urveil-lance---

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4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exception to these requirements are stated in the individual Specifications. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. During the time period:

1. From issuance of the Facility Operating License to the start of facility commercial operation, inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition, and Addenda through Summer 1975, except where specific written relief has been granted by the Commission.

2. Following start of facility commercial operation, inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), exxept where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 55.55a(g)(6)(i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection.and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

8909050424 890823 PDR P

ADOCK 05000346 PDC DAVIS-BESSE, UNIT 1 3/4 0-2 Amendment No. 71

.-.a_.-m.____._ _ _ _ . _ - _ . _ _ _ _ _ _ . _ __ _ , - _ - _ _ _ _ . - _ _ _ _ . -__-_~._._<._-~--____..______mmm_._____

Docket Number 50-345

• License Number hTF-3 O Ecrfal Number 1702 Attachment 1 Page 5 APPLICABILITY BASES 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.

4.0.2 The provisions of this specification provide allowable toler-ances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveilixace activities.

alleML- or peAan9 sarmitou cu&Wes es Theltolerancedvake;, t&. either 4r.dividually or consecut4vely ever 3 test ir.tcrvm, m sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not signifi-cantly degraded beyond that obtained from the nominal specified interval.

it is not uikncled'/fuf' &c aMwal/c fekrance. be used a:s a enwwiu /c riepe'dedi f SW MfukrM% of S<str'ti(lan< es af YQ <1/bw/>l's4k'rkice //mW, 4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operations. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or-known to be inoperable although still meeting the Surveillance Requirements.

4.0.4 This specification ensures that the surveillance activities I associated with a Limiting Condition for Operation have been performed l within the specified time interval prior to entry into an OPERATIONAL l

MODE or other applicable condition. The intent of this provision is to l ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements o.f l

the Limiting Condition for Operation.

1 DAVIS-BESSE, UNIT 1 B 3/4 0-2 L - . - - _ - - - - a

,. Docket' Number 50-346 i License Numbar NPF-3

% * 'Ser'ial Number 1702 Attachment 2

.Page 1 SIGNIFICANT HAZARDS CONSIDERATION l- i Description of Proposed Technical Specification Change The purpose of this significant hazards consideration is to review a proposed.

change to the Davis-Besse Nuclear Power Station.(DBNPS) Technical ,

Specification (TS) 3/4.0 (Limiting Conditions for. Operations and Surveillance Requirements - Applicability), Surveillance Requirement (SR) 4.0.2. ,

Surveillance Requirement 4.0.2 includes a provision that allows surveillance 1

. intervals to be extended by 25 percent of the specified time interval. This provides flexibility for scheduling the performance of surveillance and to permit consideration of plant operating conditions.that may not be suitable for conducting of a surveillance at its specified. time interval. Such conditions include transient plant operation or safety systems that may be-out-of-service due to maintenance or other ongoing. surveillance activities.

Specification 4.0.2 further limits the 25 percent allowance for extending surveillance intervals by requiring that the combined time interval for any three consecutive. surveillance not exceed 3.25 times the specified l surveillance interval. This request proposes the removal of the 3.25 limit required oy SR 4.0.2b. The Technical Description (Attachment 1) discusses L these changes.

l Significant Hazards Consideration l .The Nuclear Regulatory Commission (NRC) has provided standards in l 10CFR50.92(c) for determining whether a significant hazard exists. A proposed amendment to an Operating License for a facility involves no significant-hazards if~ operation of the facility in accordance with the proposed changes vould not: 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of l

a new or different kind of accident from any accident previously evaluated; or

3) Involve a significant reduction in a margin of safety.

The proposed changes do not involve a significant hazard because the operation of the Davis-Besse Nuclear Power Station, Unit Number 1, in accordance with these changes would:

i

1. Not involve a significant increase in the probability or consequences of i an accident previously evaluated because surveillance intervals vill still be limited by TS 4.0.2a. Additionally, the 3.25 surveillance interval extension criteria of TS 4.0.2b was not considered in the plant accident analysis [10CFR50.92(c)(1)]

2. Not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change does not add or modify any system design nor does it involve a change in operation of any plant system. The surveillance interval vill continue to be constrained by the 25 percent interval extension criteria of TS 4.0.2a.

[10CFR50.92(e)(2)]

l L-______-___________

y Dock t Numb:;r 50-346 L

Lic;nsa Nu;b;r NPF-3

'S'ifal e Number 1702 l Attachment 2-

! Page 2 3.: Not involve a significant reduction in a margin of safety because surveillance intervals vill continue to be constrained by TS 4.0.2a which l provides allowable tolerances for performing surveillance requirements beyond those specified in the normal surveillance interval.

, [10CFR50.92(c)(3)]

i conclusion Based on the discussion above, it is concluded that the proposed change does not involve a significant hazard.

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