ML20235S064

Proposed Tech Specs,Adding Requirement That Annual Rept Submitted to NRC Must Include Documentation of All Failures & Challenges to Pressurizer PORV & Safety Valves

ML20235S064
Person / Time
Site:	Millstone
Issue date:	07/14/1987
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20235S050	List: B12568, Application for Amend to License DPR-65,adding Requirement That Annual Rept Submitted to NRC Must Include Documentation of All Failures & Challenges to Pressurizer PORV or Safety Valve.Application Submitted Per 870615 Commitment.Fee Paid ML20235S064
References
TASK-2.K.3.03, TASK-TM TAC-45357, TAC-65852, TAC-66116, NUDOCS 8707210537
Download: ML20235S064 (5)

Text

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a Docket No. 50-336 B12568 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Changes to Technical Specifications July,1987 fy7210537 870734 p ADOCK 05000336 PDR

REACTOR COOLANT SYSTEM 1

SURVEILLANCE REQUIREMENTS (Continued)~

4.4.5.1.4 Acceptance Criteria

a. As used in this Specification

1. Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced crac'<ing, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

3. Degraded Tube or sleeve means a tube or sleeve containing l imperfections E 20% of the nominal wall thickness caused by degradation.

4.  % Degradation means the percentage of the tube wall or sleeve thickness affected or removed by degradation. I

5. Defect means an imperfection of sinh severity that it exceeds the plugging limit. A tube containing a defect is defective.

6. Plugging Limit means the imperfection depth at or beyond which the tube shall be repaired because it may become unserviceable prior to the next inspection and is equal to 40% g of the nominal wall thickness for tubes or sleeves.

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.1.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U - Bend to the top support of the cold leg.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging limit and plug all defecting sleeves) required by Table 4.4-6.

MILLSTONE - UNfT 2 3/4 4-7a

ADMINISTRATIVE CONTROQ_

d. Documentation of all failures (inability to lif t within the tolerances allowed by the design basis) and challenges to the pressurize PORVs or safety valves.

i MONTHLY OPERATING REPORT

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6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator, Region I, U.S. Nuclear Reguit. tory Commission, no later than the 15th of each month following the calendar month covered by. the report.

l SPECIAL REPORTS j

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6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

c. Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1.

d. ECCS Actuation, Specifications 3.5.2 and 3.5.3. l I

e. Fire Detection Instrumentation, Specifications 3.3.3.7. I I

f. Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2. )

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g. RCS Overpressure Mitigation, Specification 3.4.9.3

h. Radiological Effluent Reports required by Specifications 3.11.1.2, j 3.11.2.2, 3.11.2.3 and 3.11.4.  !

i. Degradation of containment structure, Specification 4.6.1.6.4.

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j. Steam Generation Tube Inspection, Specification 4.4.5.1.5.

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1 MILLSTONE - UNIT 2 6-19 1

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.ie ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)

Section I, Radiological Effluents Monitoring Manual, shall' outline the sampling and analysis programs to det_ ermine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It

shall also specify operating guidelines for radioactive waste treatment systems -

and report content.

Changes to Section I shall be submitted to the Commission for approval prior to l

Implementation.

.Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and IIquid effluents and in the calculations of gaseous and I liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications. Changes to Section 11 need not be submitted to the Commission for approval prior to implementation, but shall be included in the next Semi-Annual Radioactive Effluent Release Report.

'6.16 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall i specify the use of appropriate waste treatment systems utilizing the guidance

) provided in the REMODCM.

L The Solid Radioactive Waste Treatment system shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.

l 6.17- SECONDARY WATER CHEMISTRY A program shall be maintained for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shallinclude:

1. Identification of a sampling schedule for the critical variables and control points for these variables,

2. Identification of the procedures used to measure the values of the critical variables,

3. Identification of process sampling points, which shallinclude monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

4. Procedures for the recording and management of data, MILLSTONE - UNIT 2 6-23 L - _ - . - - - - - - _ - _ - - _ - - - - - _ _ _ - - _ - - - ..

o ADMINISTRATIVE CONTROLS

5. Procedores defining corrective actions for all off-control point chemistry conditions, and -

6. A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

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MILLSTONE - UNIT 2 6-24

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