Difference between revisions of "ML20136J247"

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{{#Wiki_filter:o- o CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N. CONNECTICUT P.O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 January 7,1986 Docket No. 50-213 B11947 Office of Nuclear Reactor Regulation Attn: Mr. Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate U. S. Nuclear Regulatory Commission Washington, D. C. 20555
  +
  +
==References:==
  +
(1) 3. F. Opeka letter to C. I. Grimes, dated December 6,1985,
  +
  +
==Subject:==
  +
Proposed Revision to Technical Specifications, Steam Generators Gentlemen:
  +
Haddam Neck Plant Additional Information for Proposed Revision to Technical Specifications Steam Generators In accordance with the NRC Staff verbal request of December 20, 1985, Connecticut Yankee Atomic Power Company (CYAPCO) is providing the attached additionalinformation for the proposed revision to the steam generator technical specification which was submitted by the referenced letter. The additional information clarifies that the plugging limit for sleeved steam generator tubes will be determined prior to the 1987 refueling oup for Cycle
  +
: 15. The administrative reporting requirements are also clarified to show that either plugged or sleeved steam generator tubes will be discussed in the Steam Generator Tube Inspection Report required by Technical Specification Sections 6.9.1.b.3 and 6.9.3.d.
  +
The referenced letter stated that the secondary system is filled and pressurized to identify any leaking sleeved tubes. It should be noted that this is not a hydrostatic test. Rather, it is a final check during unit restart to identify primary to secondary leakage.
  +
CYAPCO has reviewed the attached proposed change pursuant to the requirements of 10CFR50.59 and 10CFR50.92 and has determined that it does not constitute a change to the safety evaluation or significant hazards consideration previously submitted with the referenced letter.
  +
8601130292 86010723 acq Ad. e,a en9 u l)
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DR ADOCK O y , ,
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.We trust you find this information satisfactory and request review and approval of this additional information by March 1,1986 in order to support the start of Cycle 14.
  +
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY M- [1,tfL r J. F. Op4ka - O Senior Vice President
  +
' Attachment 4
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} ,. Docket No. 50-213 t
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1 a- Attachment s
  +
Haddam Neck Plant Additional Information for Proposed
  +
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  +
,, Revision to Technical Specifications,
  +
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  +
- Steam Generators
  +
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a) 1 A seismic. occurrence greater than the operating basis 7 earthquake.-
  +
b) ' A . loss of coolant accident which causes significant deviations in temperature or pressure which affect the
  +
- integrity of the steam generator tubes, or requires J
  +
. actuation of the engineered safeguards.
  +
;c) _ A major steam line or major feedwater line break.
  +
D. Acceptance Criteria:
  +
1
  +
} 1.- As used in this Specification: I a)' Imperfection means an exception to the dimensions,
  +
.. finish : or . contour of a tube . from that required by fabrication drawings .or specifications. ' Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as
  +
. imperfections, b) Degradation' means a service-induced cracking, wastage, pitting, wear or general corrosion occurring on either
  +
- inside or outside of a tube.
  +
c) ~ Degraded Tube means a tube containing imperfections 20 % of the nominal wall thickness. caused by degradation. -
  +
d)- % Degradation means the percentage of the tube wall thickness affected. or removed by degradation.
  +
e) _ Defect means an imperfection of such severity thatit
  +
, exceeds the plugging limit. A tube or sleeve containing a defect is defective.
  +
f . f) Plugging Limit means the' imperfection depth at or beyond which the tube or sleeve shall be removed from service because it may' become' unserviceable prior to the next inspection and is equal to 50% of the nominal tube wall thickness for tubes.*
  +
~ *The plugging'' limit for sleeves will be determined prior to the 1987 refueling Joutage for Cycle 15.
  +
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  +
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  +
  +
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  +
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: 3) Identification of tubes either plugged or sleeved.
  +
: c. ~ Occupational Exposure Report
  +
-The annual report shall be submitted prior to March 1 of each year and shall cover the previous calendar year. The initial report shall 1 be submitted prior. to March - 1 of the year following initial
  +
, , : criticality.
  +
This annual report shall include a tabulation on an annual basis of the number of station, -utility, and other personnel (including contractors) receiving exposures _ greater than 100 mrem /yr. and 2
  +
their associated man-rem exposure according to work and job functions,1/e.g., Lreactor operations and surveillance; inservice inspection, routine maintenance, - special maintenance (describe maintenance), waste- processing and refueling. The dose
  +
$ assignment to various duty functions may be estimated based on
  +
. pocket dosimeter, TLD, or - film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total
  +
, .whole body dose received from external sources shall be assigned
  +
' to specific major work functions.
  +
: d. Monthly-Operating Report - Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D. C.
  +
20555, with a copy to the appropriate Regional Office, to be
  +
: postmarked no later than the fifteenth of each month following the -
  +
calendar month covered by the report.
  +
The monthly report shallinclude a narrative summary of operating experience during the report period relating to safe operation of.
  +
the facility, including safety-related maintenance.
  +
e.- Reports required as per 10 CFR 50.59b.
  +
-6.9.2 - Reportable Occurrences
  +
. Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.
  +
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
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ads 11NISTRATIVE CONTROLS SPECIAL REPORTS 6.9.3 Special reports shall be. submitted to the Regional Administrator of the
  +
- Regional Office 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. - hservice Inspection results, Specifications (4.10) and (4.12).
  +
: b. Primary Containment Leak Rate Results, Specification (4.4).
  +
: c. Reactor Vessel Material Surveillance Specimen Examination,
  +
.; - Specification (4.10).
  +
: d. Steam Generator Tube Report Following each inservice inspection of steam generator tubes, the number of tubes either plugged or sleeved in each steam generator shall be reported to the Commission within 15 days. l
  +
: e. Post-Accident Instrumentation Operability, Specification (3.23 A and B).
  +
6.10 . RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
  +
: a. Records and logs of facility operation covering the time interval at each power !evel.
  +
: b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
  +
: c. Reports of all events which are required by regulations and Technical Specifications to be reported to the NRC in writing within 24 hours.
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: d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
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Latest revision as of 02:18, 1 July 2020

Forwards Addl Info on 851206 Proposed Rev to Steam Generator Tech Spec,In Response to 851220 Verbal Request.Plugging Limit for Sleeved Steam Generator Tubes Will Be Determined Prior to 1987 Refueling Outage for Cycle 15
ML20136J247
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 01/07/1986
From: Opeka J
CONNECTICUT YANKEE ATOMIC POWER CO.
To: Charemagne Grimes
Office of Nuclear Reactor Regulation
References
Download: ML20136J247 (6)


Text

o- o CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N. CONNECTICUT P.O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 January 7,1986 Docket No. 50-213 B11947 Office of Nuclear Reactor Regulation Attn: Mr. Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate U. S. Nuclear Regulatory Commission Washington, D. C. 20555

References:

(1) 3. F. Opeka letter to C. I. Grimes, dated December 6,1985,

Subject:

Proposed Revision to Technical Specifications, Steam Generators Gentlemen:

Haddam Neck Plant Additional Information for Proposed Revision to Technical Specifications Steam Generators In accordance with the NRC Staff verbal request of December 20, 1985, Connecticut Yankee Atomic Power Company (CYAPCO) is providing the attached additionalinformation for the proposed revision to the steam generator technical specification which was submitted by the referenced letter. The additional information clarifies that the plugging limit for sleeved steam generator tubes will be determined prior to the 1987 refueling oup for Cycle

15. The administrative reporting requirements are also clarified to show that either plugged or sleeved steam generator tubes will be discussed in the Steam Generator Tube Inspection Report required by Technical Specification Sections 6.9.1.b.3 and 6.9.3.d.

The referenced letter stated that the secondary system is filled and pressurized to identify any leaking sleeved tubes. It should be noted that this is not a hydrostatic test. Rather, it is a final check during unit restart to identify primary to secondary leakage.

CYAPCO has reviewed the attached proposed change pursuant to the requirements of 10CFR50.59 and 10CFR50.92 and has determined that it does not constitute a change to the safety evaluation or significant hazards consideration previously submitted with the referenced letter.

8601130292 86010723 acq Ad. e,a en9 u l)

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DR ADOCK O y , ,

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.We trust you find this information satisfactory and request review and approval of this additional information by March 1,1986 in order to support the start of Cycle 14.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY M- [1,tfL r J. F. Op4ka - O Senior Vice President

' Attachment 4

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1 a- Attachment s

Haddam Neck Plant Additional Information for Proposed

.. g

,, Revision to Technical Specifications,

.r 3 ,

- Steam Generators

-i .

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d January,1986 J

4 u-I I

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a) 1 A seismic. occurrence greater than the operating basis 7 earthquake.-

b) ' A . loss of coolant accident which causes significant deviations in temperature or pressure which affect the

- integrity of the steam generator tubes, or requires J

. actuation of the engineered safeguards.

c) _ A major steam line or major feedwater line break.

D. Acceptance Criteria:

1

} 1.- As used in this Specification: I a)' Imperfection means an exception to the dimensions,

.. finish : or . contour of a tube . from that required by fabrication drawings .or specifications. ' Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as

. imperfections, b) Degradation' means a service-induced cracking, wastage, pitting, wear or general corrosion occurring on either

- inside or outside of a tube.

c) ~ Degraded Tube means a tube containing imperfections 20 % of the nominal wall thickness. caused by degradation. -

d)- % Degradation means the percentage of the tube wall thickness affected. or removed by degradation.

e) _ Defect means an imperfection of such severity thatit

, exceeds the plugging limit. A tube or sleeve containing a defect is defective.

f . f) Plugging Limit means the' imperfection depth at or beyond which the tube or sleeve shall be removed from service because it may' become' unserviceable prior to the next inspection and is equal to 50% of the nominal tube wall thickness for tubes.*

~ *The plugging limit for sleeves will be determined prior to the 1987 refueling Joutage for Cycle 15.

^ 4-21c 4

"f.

n -

1 y, 1;

~

l

3) Identification of tubes either plugged or sleeved.
c. ~ Occupational Exposure Report

-The annual report shall be submitted prior to March 1 of each year and shall cover the previous calendar year. The initial report shall 1 be submitted prior. to March - 1 of the year following initial

, , : criticality.

This annual report shall include a tabulation on an annual basis of the number of station, -utility, and other personnel (including contractors) receiving exposures _ greater than 100 mrem /yr. and 2

their associated man-rem exposure according to work and job functions,1/e.g., Lreactor operations and surveillance; inservice inspection, routine maintenance, - special maintenance (describe maintenance), waste- processing and refueling. The dose

$ assignment to various duty functions may be estimated based on

. pocket dosimeter, TLD, or - film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total

, .whole body dose received from external sources shall be assigned

' to specific major work functions.

d. Monthly-Operating Report - Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D. C.

20555, with a copy to the appropriate Regional Office, to be

postmarked no later than the fifteenth of each month following the -

calendar month covered by the report.

The monthly report shallinclude a narrative summary of operating experience during the report period relating to safe operation of.

the facility, including safety-related maintenance.

e.- Reports required as per 10 CFR 50.59b.

-6.9.2 - Reportable Occurrences

. Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

n p

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E _ _

'a c: ;o.

ads 11NISTRATIVE CONTROLS SPECIAL REPORTS 6.9.3 Special reports shall be. submitted to the Regional Administrator of the

- Regional Office 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. - hservice Inspection results, Specifications (4.10) and (4.12).
b. Primary Containment Leak Rate Results, Specification (4.4).
c. Reactor Vessel Material Surveillance Specimen Examination,

.; - Specification (4.10).

d. Steam Generator Tube Report Following each inservice inspection of steam generator tubes, the number of tubes either plugged or sleeved in each steam generator shall be reported to the Commission within 15 days. l
e. Post-Accident Instrumentation Operability, Specification (3.23 A and B).

6.10 . RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering the time interval at each power !evel.
b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c. Reports of all events which are required by regulations and Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

6-22 l _