ML20245D869
| ML20245D869 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  (DPR-49-A-157) |
| Issue date: | 04/18/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245D870 | List: |
| References | |
| NUDOCS 8905010205 | |
| Download: ML20245D869 (7) | |
Text
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tag UNITED STATES I
NUCLEAR REGULATORY COMMISSION o-O e E WASHINGTON, D. C. 20665 4,.....
IOWA ELECTRIC LIGHT AND POWER COMPANY cEMIRAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE
-DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 157 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.-
The application for amendment by Iowa Electric Light and Power Company, et al., dated October 14, 1986, as revised March 25, 1987, 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;
-B.
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 Commission's regulations; D.
The issuance of this anendment w.
. not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendnent is in accordance with 10 CFR Part Si of the Commission's regulations and all applicable requirements have been satisfied.
- 2. -
Accordingly, the license is amended by changes to the Technical Specifi-b-
cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of facility Operating License No. OPR-49 is hereby amended to read as follows:
890501020589pg31 PDR ADOCK O pg s P
-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.157, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$;=a=
John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1989 l
1 1
A_T,TACW,ENT TO LICENSE AMENDMENT N0.157 T
FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 i
Replace the following pages of the Appendix A Techn?.a1 Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
l Pages l
l l
6.5-2 6.5-7 6.5-9 6.8-2 1
m DAEC-1 4-4 L-
- 6. 5.1. 4 Meel.ing Frequency i
Tbc Operations Committee shall meet at least once per calendar month and as convened by the Operations Committee Chainnan or Vice Chairman.
l 6.5.1.5-Quorum A quorum of the Operations Committee shall consist of the Chairman or Vice Chairman and five members including alternates.
6.5.1.6 Responsibilities The Operations Committee shall be responsible for:
a.
Review of (1) all procedures required by Specification 6.8, Plant Operating Procedures, and changes thereto, (2) any other proposed procedures or changes thereto as determined by the Plant Superinten-dent-Nuclear to affect nuclear safety, b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Technical Specifications.
l d.
Review of all proposed changes or modifications to plant systems or equipment that affect n: ciear safety.
i i
I Amendment No. M, 157 6.5-2 l
p DAEC-1 p
65.2.7fReview The Safety Committee shall be responsible for the review of:
a.
The safety evaluations for'(1) changes to procedures, and (2) tests or experiments completed under'the provision of.Section 50.59,
'10 CFR, to verify'that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed 'afety question as defined in Section 50.59, 10 CFR.
s c.
Proposed. tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or licenses..
e.
Violations of applicable statutes, codes, regulations, orders, r
technical specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations' from normal and expected performance of plant equipment that affect nuclear safety.
I i
g.
All Reportable Events.
h..
All recognized ir,dications of an unanticipated deficiency in some
)
aspect of design or operation of safety-related structures, systems,-
or corrponents.
' Amendment No. 195, 157 6.5-7 I
o
.i
DAEC-1 e
g.
Any other area of. facility operation considered appropriate by the Safety Committee or the President.
h.
Design change package safety evaluations at least once per 24 months.
l 1.
The DAEC Fire Protection Program and implementing procedures at least once per 24 months.
- j. The Process Control Program and implementing procedures at least once per 24 months.
k.
The Offsite Dose Assessment Manual and implementing procedures at least once per 24 months.
1.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
m.
Performance of activities required by the QC Program for effluent and the vendors QA Program for radiological environmental monitoring.
6.5.2.9 Authority The Safety Committee shall report to and advise the President on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
6.5.2.10 Records Records of Safety Committee activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each Safety Committee meeting shall be prepared, approved and forwarded to the President within 14 days following each meeting.
Amendment No. JM,157 6.5-9 ca_____-____.
DAEC-1 L.
8.
Procedures required by the plant Security Plan.
9.
Operation of radioactive waste systems.
10.
Fire Protection Program implementation.
11.
A preventive maintenance and periodic visual examination program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient to as low as practical levels. This program shall also include provisions for performance of periodic systems leak tests of each system once per operating cycle.
12.
Program to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions, including training of personnel, procedures for monitoring and provisions for maintenance of sampling and analysis equipment.
13.
Administrative procedures for shift overtime for Operations personnel to be consistent with the Commission's June 15, 1982 policy statement.
14.
Offsite Dose Assessment Manual.
15.
Process Control Plan.
16.
Quality Control Program for effluents.
6.8.2 Procedures described in 6.8.1 above, and changes thereto, shall be reviewed by the Operations Committee as indicated in Specification 6.5.1.6 and approved by the Plant Superintendent-Nuclear prior to implementation, except as provided in 6.8.3 below.
6.8.3 Temporary minor changes to procedures described in 6.8.1 above which do not change the intent of the original procedure may be made with the concurrence of two members of the plant management staff, at least one of whom shall hold a senior operator license.
Such changes shall be documented and promptly reviewed by the Operations Committee and by the Plant Superintendent-Nuclear.
Subsequent incorporation, if necessary, as a permanent change, shall be in accord with 6.8.2 above.
Amendment No. Jpp,J76,118,JD,157 6.8-2
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