ML20247D032

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Amend 119 to License DPR-69,modifying Tech Spec 3/4.7.8, Snubbers, by Providing one-time Extension to Max Surveillance Interval of 18 Months Plus 25% for Conducting Snubber Functional Tests
ML20247D032
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 03/24/1989
From: Capra R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247D029 List:
References
NUDOCS 8903300354
Download: ML20247D032 (7)


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UNITED STATES NUCLEAR REGULATORY COMMISSION 5 g WASHINGTON, D. C. 20665

\...../ BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO 50-318-CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. DPR-69

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Baltimore Gas and Electric Company (the licensee) dated October 14, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; R. The facility will operate-in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The -issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and-E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comnission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragr4 h 2.C.2 of Facility Operating License No.

DPR-69 is hereby amended to read as follows:

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8903300354 890324 gDR ADOCK0500g8 l

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I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119 , are hereby incorporated in the license. The. licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COP 911SSION b~Ud Bxx Robert A. Capra, Director h Project Directorate I-1 Division of Reactor Projects, I/II

Attachment:

Changes to the. Technical Specifications Date of Issuance: March 24, 1989

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 119 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Revise Appendfx A as follows:

Remove Pages Insert Pages 3/4 7-25 3/4 7-25 3/4 7 3/4 7-26 3/47-26{t)I 1 Page 3/4.7-26(t) contains a temporary change that is effective until 11:59 p.m. on May 17, 1989 or until reaching 199.9'F average reactor coolant system (RCS) temperature during initial RCS heatup following the Unit 2 Cycle 9 refueling outage.

2 Page 3/4 7-26 replaces page 3/4 7-26(t).

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I PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION i

3.7.8.1 l All safety related snubbers shall be OPERABLE.

APPLICABILITY: liODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status, and perform an engineering evalua-tion

  • per Specification 4.7.8.1.b and c on the supported component or declare the l supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.8.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. As used in this Specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.

a. Visual Inspections Visual inspections shall be perfomed in accordance with the following schedule:

No. Inoperable Snubbers of Subsequent Visual **

Each Type per Inspection Period Inspection Period #

0 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days 1 25%

5,6,7 62 days 1 25%

8 or more 31 days 1 25%

The snubbers may be further categorized into two groups: Those accessible and those inaccessible during reactor operation. Each

. group may be inspected independently in accordance with the above schedule.

1 Safety related snubbers include those snubbers installed on safety related systems and snubbers on non-safety related systems if their failure or the failure of the system on which they are installed would have an adverse effect on any safety related system.

A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation. Additional analyses, as needed, shall be completed in a reasonable period of time.

    • The inspection interval shall not be lengthened more than two steps at a time.
  1. The provisions of Specification 4.0.2 are not applicable.

CALVERT CLIFFS - UNIT 2 3/4 7-25 Amendment No.19,H,J99, M6.

119

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. . j PLANT SYSTEMS  !

SURVEILLANCE REQUIREMENTS (Continued) _

b. Visual Inspection Acceptance Criteria Visual inspections shall v6rify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures. Snubbers which appear inoper-able as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.1.d, as applicable. When the fluid port of a hydraulic snubber is found to be uncovered, the snubber y' l shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

For the snubber (s) found inoperable, an engineering evaluation shall be perfonned on the component (s) which are supported by the snubber (s). The scope of this engineering evaluation shall be consistent limited to a visual with the licensee's inspection engineering of the supported judgment componentand(s . may)be The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

c. Functional Tests At least once per 18 months
  • during shutdown, a representative sample of 10% of each type of snubbers in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.1.d, an additional 5% of that type snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.

In addition to the surveillance interval extensions permitted by Specification 4.0.2, a one-time, temporary amendment of Surveillance Requirement 4.7.8.1.c shall provide a schedular extension of up to 54 days for the performance of the snubber functional tests. This extension expires at 11:59 p.m. on May 17. 1989 or upon reaching 199.9'T average reactor coolant system (RCS) temperature during initial RCS heatup following the Unit 2 Cycle 9 refueling outage, whichever occurs first.

CALVERT CLIFFS - UNIT 2 3/4 7-26(t) Amendmen t No. J9,38,H ,73,196,119

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I PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8.1 l All safety related snubbers shall be OPERABLE.

APPLICABILITY: liODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status, and perfonn an engineering evalua-l tion

  • per Specification 4.7.8.1.b and c on the supported component or declare the j supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREtiENTS 4.7.8.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. As used in this Specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.

a. Visual Inspections Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers of Subsequent Visual **

Each Type per Inspection Period Inspection Period #

0 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days 1 25%

5,6,7 62 days 1 25%

8 or more 31 days 1 25%

The snubbers may be further categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.

l 1 Safety related snubbers include those snubbers installed on safety related systems and snubbers on non-safety related systems if their failure or the ]

failure of the system on which they are installed would have an adverse effect on any safety related system. ]

  • A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation. Additional analyses, as needed, shall be completed in a reasonable period of time.
    • The inspection interval shall not be lengthened more than two steps at a time.
  1. The provisions of Specification 4.0.2 are not applicable.

CALVERT CLIFFS - UNIT 2 3/4 7-25 Amendment No. J9,H ,J99, 106, 119 -)

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. . E PLANT SYSTEMS l

SURVEILLANCE REQUIREMENTS (Continued) I

b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no' visual indications of detachment from foundations or supporting structures. Snubbers which appear inoper-able as a result of visual inspections may be detemined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.1.d, as applicable. When the fluid l port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s). The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspection of the supported component (s).

The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

c. Functional Tests At least once per 18 months
  • during shutdown, a representative j sample of 10% of each type of snubbers in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.1.d. an additional 5% of that type j snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.

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  • Effective at 11:59 p.m. on May 17, 1989 or upon reaching 199.9'F average reactor coolant system (RCS) temperature during initial RCS heatup following the Unit 2 Cycle 9 refueling outage, whichever occurs first.

Replaces page 3/4 7-26(t).

CALVERT CLIFFS - UNIT 2 3/4 7-26 Amendment No.19.)S.#f,7),100' 119 '

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