ML19274D852
| ML19274D852 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/14/1979 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902260458 | |
| Download: ML19274D852 (12) | |
Text
..s CONNECTICUT YANKEE AT O M IC POWER COMPANY BERLIN, CO N N EC TIC U T P
O. BOX 270 H ARTFORD. CON N ECTICUT 06101 20s e s 911 February 14, 1979 Docket No. 50-213 Director of Nuclear Reactor Regulation Attn: Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Gentlenen:
Reference:
(1) D. C. Switzer letter to A. Schwencer dated June 29, 1977.
Haddam Neck Plant Proposed Changes to Technical Specifications Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPC0) hereby proposes to amend its operating license No. DPR-61 by incorporating the attached (Attachments 1 and 2) proposed changes into the Technical Specifications for the Haddam Neck Plant.
The proposed changes in Attachment 1 supersede the proposed license amendment request forwarded in Reference (1). These changes revise the removal schedule for the reactor vessel surveillance capsules at the Haddam Neck Plant to provide confonnance with the criteria of 10CFR50 Appendix H.
The proposed Technical Specifications in Attachment 2 reflect organizational and administrative changes within CYAPC0.
A technical review of the proposed changes has been perfonned. The review of the specifications in Attachment I concluded that these changes will extend the Inservice Inspection (ISI) Program, now applied to the reactor coolant system pressure boundary, to safety-related components throughout the plant. As such, the proposed revisions will further assure the continued structural integrity of the applicable components.
The proposed changes in both attachments were found technically acceptable. A safety evaluation was also performed and has concluded that these specifications do not constitute any unreviewed safety questions.
The Connecticut Yankee Nuclear Review Board has reviewed and approved the pro-posed specifications and has concurred with the above detennination.
790226o4SF
. CYAPC0 has reviewed the above proposed license amendment pursuant to the require-ments of 10CFR170, and has detennined that the proposal in Attachment 2 constitutes a Class 2 amendment. Accordingly, enclosed herewith is payment in the amount of
$1,200 (one thousand, two hundred dollars). The basis for this determination is that these changes are administrative in nature and have no safety or environmental significance. With regard to the proposal in Attachment 1, these specifications are a revision to the original proposed specifications sutmitted to the NRC Staff in Reference (1), with the only change from those in Reference (1) being a re-vision to the surveillance capsule removal schedule.
Since these revisions will not alter or increase the review effort which would have been required of the NRC Staff by Reference (1), CYAPC0 has concluded that licensing fees are not applicable. This determination has been discussed between CYAPC0 and the NRC Staff.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY l'
VN!
W. G. Counsil Vice President Attachments
STATE OF CONNECTICUT )
A
)
ss. Berlin
/(, / N COUNTY OF HARTFORD
)
Then personally appeared before me, W. G. Counsil, who being duly sworn, did state that he is Vice President of Connecticut Yankee Atomic Power Company, the Licensee herein, th.
ne is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
N ha$
Notary Public My Commiss!:a Expires M:rch 31,1531
Docket No. 50-213 ATTACHMENT 1 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS HADDAM NECK PLANT
.e January, 1979
SECTION 4.0 SURVEILLANCE REQUIREMENTS PAGE 4.1 Introduction 4-1 4.2 Operational Safety Items 4-2 4.3 Core Cooling Systems - Periodic Testing 4-3 4.4 Containment Testing 4-5 4.5 Emergency Power System Feriodic Testing 1-11 4.6 Radioactive Liquid Waste Release 4-13 4.7 Radioactive GaseJus Waste Release 4-15 4.8 Auxiliary Steam Generator Feed Pump 4-17 4.9 Main Steam Isolation Valves 4-18 4.10 Inservice Ins,ction and Reacto" Vessel Surv.
4-19 4.11 DELEiED l
4.12 High Energy Piping System Tests 4-24 4.13 Hydraulic Snubbers 4-26 SECTION 5.0 DESIGN FEATURES 5.1 Introduction 5-1 5.2 Site Description 5-1 5.3 Reactor 5-2 5.4 Containment 5-4 III
4,10 Inservice Inspection and Reactor Vessel Surveillance Apolicability: Applies to the periodic inservice inspection and testing of ASME Boiler and Pressure Vessel Code Class 1, 2, and 3 equivalent components, Objective: To verify the structural integrity of the applicable components defined above, Specification:
A.
Inservice Inspection of ASME Code Class I, C1' ass 2 and Class 3 equivalent comprnents 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), with the exemptions and alternate inspecic'ons that have been approved by the NRC pursuant to 10 CFR 50, Section 10.55a(g) (6) (1). These exemptions and alternate inspections are included in the Inservice Inspection Program.
B.
Inservice testing of ASME Code Class 1, Class 2 and Class 3 equiv-alent pumps and valves shall be performed in accordanca with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 30,55(g), with the exemptions and alternate testing that have been approved by the NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (1). These exemptions and alternate testing are included in the Inservice Inspection Program C.
One reactor coolant pump flywheel shall be examined visually and 100% volumetrically every other refueling.
D.
The removal plan for the remaining reactor vessel surveillance capsules is scheduled as follows:
Capsule Capsule Removal Time Predicted Exposure (E > 1MEV) N/CM2 Type Ident.
Years
- Capsule Reactor Vessel ID I
H 10 1,3x1019 1.0x1019 19 II D
15 2.0x10 1.6x1019 II E
25 3.3x1019 2.6x1019 I
B Standby I
C Standby I
G Standby
- Removal time is in approximate calendar years from the date of initial criticality (July 24, 1967) and intended to coincide with the nearest refueling outage to that time.
4-19
Basis 10 CFR 50.55a(g) sets forth the inspection requirements for nuclear power plant components for reference 1ng the ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components" which defin9.: the requirements for inspection of ASME Code Class 1, 2, and 3 equivalent components.
In regards to the reactor surveillance capsule program there are only two capsules (Type II) containing specimens of weld metal remaining. Therefore, the first of these will not be removed until 15 years of operation have elapsed and the second until 25 years have elapsed. This will provide the greatest amount of useful information about irradiation effects on weld metal over the lifetime of the plant.
In addition, removal of the Type I capsule at the 10 year point will confirm the noted trends and will leave three Type I capsules in standby for special purposes.
4-20
e DELETED 4-21
4 DELETED 4-22
Docket No. 50-213 ATTACHMENT 2 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS HADDAM NECK PLANT January, 1979
HADDMI NECK PIANT STATION SUPERINTENDENT ORCANIZAff0N CPART CONNECTICUT TANKEE ATOMIC PMR COMPANY ASSISTANT STATION SUFFRINTENDENT NUCLEAR RECORDS ENERCT INFORMATION CENTER QUALITY ASSURANCE SECURITT ENCINEERING TRAINING SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR 3
f.JCLEAR RECORDS INERCT INFORMATION CENTER QUALITY ASSURANCE ENT.INFERING TRAINING PERSONNEL PERSONNE!.
PF.R SONN F.L PP.RSONNEL PERSONNEL (h
Iu I
OPERATIONS MAINTENANCE INSTRUMENTATION AND CONTROL HF.ALTH PHYSICS CHDf!ST tY OrPICE SUPf.RVISOR SUFFRVISOR SUPERVISOR SUPERVISOR SUFFRVISOR SUPERVISOR.
l OFFICE PIRSONNEL OPERATIONS MAINTtNANCE INSTRUMFNTATION AND CONTROL HEALTH PHYSICS CHINISTRY PERSONNEL PERSONNEL PtRSONNLL PtpSONNFL PCRSONMFL BUILDING MAINTENANCE PFRSONNFL STORES SUFFRVISOR STORl'S PFRSONNEL FIGURE 6.2.2
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Station Superintendent Member:
Assistant Station Superintendent Member:
Operating Supervisor Member:
Maintenance Supervisor Member:
Inntrument and Control Supervisor Member:
Reactor Engineer Member:
Chemistry Supervisor Member:
Engineering Superv sor Member:
Health Physics Supervisor Member:
Quality Assurance Supervisor 6-Sa
.