ML20129E977

Amend 66 to License DPR-54,changing Tech Specs to Add Surveillance of Certain Special Interest Steam Generator Tubes & Visual Insps of Internal Auxiliary Feedwater Distributor,Attachment Welds & Thermal Sleeves

ML20129E977
Person / Time
Site:	Rancho Seco
Issue date:	05/28/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129E951	List: ML20129E945 ML20129E977 ML20129F009
References
TAC-52307, NUDOCS 8506060648
Download: ML20129E977 (10)

Text

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$ .: j WASHINGTON, D. C. 20555

\*****/ SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-54

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

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated September 9, 1982, as revised December 28, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) 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 Comission'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 paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

8506060648 DR 850528 p ADOCK 05000312

PDR V.

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66 , 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION r

oh . tol , Chief Ope ating Reactors Branch #4 ision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 28, 1985 e

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ATTACHMENT T0itICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace'the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert vi vi ix ix 4-54 4-54 4-55 4-55 4-55'a 4-57a 4-57L 1

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RANCHO SECO UNIT 1 TECHNICAL. SPECIFICATIONS TA3LZ OT wamis (con:inued)

See: ton -

Pare-4.14 SEDCK StlFFIZSSORS (53U3 BETS) 4-47 4.15 , EADIDACTIYZ MA m m t SCU2CIS 4-43 4.16 Rasarved 9 49

• 4.17 STIAM N ORS 4-51 4.17.1 Stama Generator Smaple Salaccion and Inspec ion 4-51 4.17.2 Staan Generator Tube Sample Selection and Inspec ion 4-51 4.17.3 Inspection Frequencias 4-32 4.17.4 Acceptance Crt:eria 4-33

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4.17.3 Raports 4-54 4.17.G OTSG Auxiliary Feedwater Header Surveillance 4-54 4.17.7 Inspection Acceptance Criteria and Corrective Actions 4-55 4.17.8 Reports 4-55 4.13 1"I1Z SUFF3ZSSION STSTZM SNCE 4-58 4.19 RADIOACTIVE LIQUID EFFLUE!!T I!!STRUf1ENTATION 4-63 4.20 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-65 4.21 LIQUID EFFLUENTS 4-69 4 .21 .1 Concentration 4-69 4.21.2 Dose Calculations 4-72 4.21.3 - Licuid Holdup Tanks 4-73 4.22 GAS,EO.US,, EFFLUENTS 4-74 4.22.1 Dese Rate 4-74 4.22.2 Noble Gases 4 77 4.22.3 Iodine-131, Tritium and Radionuclides in Particulate Form 4-78 4.23 GASEOUS RADWASTE TREATMENT 4-79 4.24 GAS STORAGE TANKS 4-80 4.25 SOLID RADI0 ACTIVE WASTES 4-81 4

1 Amendment No. 25, 5),66 yt q.-

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RANCHO SECO UNIT 1- '

TECHNICAL SPECIFICATIONS

, LIST OF TABLES 2.3-1 -

REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9

3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.14-l' FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55

! 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.1G-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83

- 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 ,

, IN ENVIRONMENTAL SAMPLES  !

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4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 l 4 1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 .;

4.1-3 MINIMUM SAMPLING FREQUENCY 49 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-8 ESSE 1 4-12a 4.2-2 INSERVICE INSPECTION SCHEDULE 4-13

] i 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 4.10-2 -

OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-224 4.14-1 SNU88ERS ACCESSIBLE DURING POWER OPERATIONS 4 47c  :

- i I 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE 4-56 INSPECTED DURING INSERVICE INSPECTION 4.17-2 STEAM GENERATOR TUBE INSPECTION 4-57 4.17-3 , OTSG AUXILIARY FLEDWATER HEADER SURVEILLANCE 4-57a, 4-57b 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 i SURVEILLANCE REQUIREMENTS 4.20-1 RADIDACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS i

!. U l'- Amendment No. 28, D,66 l ,

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS L

Surveillance Standards 4.17.4 Acceptance Criteria

3. Degraded Tube means a tube containing imperfections >20% of sne nominal wall thickness caused by degradation.

-4. Defective Tube means a tube containing an imperfection >40%

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of the nominal tube wall thickness unless higher limits are

-shown acceptable by analysis. Defective tubes shall be plugged.

5. Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit (except as noted in 4.17.2c).

b. The steam generator shall be determined OPERABLE after completing the corresponding actions required by Table 4.17-2.

4.17.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Comiission within 15 days.

b. The results of the' steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed. This report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged.

c. Results of steam generator tube inspections which fall into Category C-3 and require notification of the Commission shall be reported pursuant to Specification 6.9 prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

4.17.6 OT5G Auxiliary Feedwater Header Surveillance On the first refueling outage following the 1983 refueling outage, and at the 10-year ISI, the following inspections will take place:

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p. 4-54 L

Amendment flo J),66 '

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RANCHO SECO UNIT 1  :

TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.6 - a. Visual inspections of'the secured Internal Header, attachment welds and external headers therraal sleeves will be made through selected openings, .and will be performed in such a manner that the known cracks in the Internal Header will be inspected.

b. Selected special interest peripheral tubes, designated in Table 4.17-3. will be Eddy Current inspected but shall not be considered a part of the Eddy Current inspection that is conducted pursuant to Technical Specification 4.17.1 through 4.17.5.

4.17.7 Inspection Acceptance Criteria and Corrective Actions

a. Video taped inspections of the known cracks perfomed during the initial discovery will be compared with the crack configuration found during this surveillance. This comparison will allow 4 determination to be made as to whether or not the crack has propagated.

b. If any inspected special interest peripheral tube indicates [

clearance (less than 1/4") or greater than 40% through wall

indications, it will be plugged.

4.17.8 Reports ,

A report of these inspections will be prepared and incorporated in the subsequent Monthly Report to the NRC.

gases  !

The Surveillance Requirouents for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The surveillance requirements of steam generator tubes are based on a modification of B&W - Standard Technical Specifications dated June 1 1976. Inservice inspection of steam generator tubing is essential in order to L maintain surveillance of the conditions of the tubes in the event that there is

evidence of mechanical damage or progressive degradation due to design, i manufacturing errors, or inservice conditions that lead to corrosion.

l- Inservice inspection of steam generator tubing also provides a means of i characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

l Wastage-type defects are unlikely with AVT chemistry treatment of the

secondary coolant. However, even if a defect should develop in service, it j will be found during scheduled inservice steam generator tube examinations.

l plugging will be required for defective tubes. Steam generator tube inspections of operating plants have demonstrated the capability to reliably

! detect degradation that has penetrated 20% of the original tube wall thickness.

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' Amendment flo. D, G6 ' 4-55

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Bases (Continued)

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.9 prior to resuuption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional ed@-current inspection and revision of the Technical Specifications, if necessary.

The visual and ed# current inspections provide the capability of determining the success of the internal aux feedwater header stabilization by monitoring the long tem effects to tube integrity and crack propagation. The inspections will focus on known crack growth, new crack identification (if any), and tube effects in localized areas near the internal header brackets.

Additionally, visual inspection of the external header thermal sleeves will provide assurance that the new design header will not introduce additional problems by demonstrating sleeve integrity.

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. Amendment tio. JJ,66 4-55a L

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RANCHO SECO UNIT 1 i . TECHNICAL SPECIFICATIONS Surveillance Stanaarus TABLE 4.17-3 OTSG Auxiliary Feedwater Header Surveillance OTSG A Special Interest Tubes Row Tube No 5 1, 46 6 2, 3, 49, 50, 51 7 1, 2, 53, 54 8 1, 2, 66, 57 44 1, 119 45 1, 120 46 1, 121 47 1, 122 48 1, 123

'49 1, 124 103 1, 124 105 1 106 1, 119 107 1, 120 108 1, 119 144 1, 2, 56, 57 145 1, 2, 53, 54 146 2, 3, 49, 50 , 51 147 1, 46 Amendment flo, GG' 4-67a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TA8LE 4.17 3 (Continued)

OTSG Auxiliary Feedwater Header Surveillance OTSG 8 Special Interest Tubes Row Tube No 5 1, 46 6

2, 3, 49, 50 7 1, 2, 53, 54 8 1, 2, 56, 57 44 1, 119 45 1, 120 46 1, 121

, 47 122 48 1, 123 49 1, 124 103 1, 124 104 123 105 122 106 1, 119 107 1, 120 108 1, 119 144 1, 2, 56, 57 145 -

1, 2, 53, 54 146 2, 3, 49, 50, 51 147 1, 46 l

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l- Amendnent No. 65 4-57b l*

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