ML20237K266
| ML20237K266 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/13/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Spangenberg F ILLINOIS POWER CO. |
| References | |
| NUDOCS 8708190170 | |
| Download: ML20237K266 (4) | |
Text
August 13, 1987 DISTRIBUTION,
' 4 4 u rue A Docket No.: 50-461
GHalahan l
Mr. Frank A. Spangenberg M0'Brien
(
Manager - Licensing and Safety Clinton Power Station BSiegel P.' O. Box 678 OGC-Bethesda Mail Code V920.
EJordan Clinton, Illinois 61727 JPartlow
Dear Mr. Spangenberg:
SUBJECT:
CHANGE TO BASES SECTION 3/4.7.4 0F CLINTON TECHNICAL SPECIFICATIONS By letter dated July 15, 1987, Illinois Power Company submitted a proposed-change to the Technical Specification appended to Facility Operating License No. NPF-62 for Clinton Power Station. The proposed changes would modify BASES Section 3/4.7.4 of the Technical Specification to permit the accessibility of each snubber to be determined by the Facility Review Group (onsii.e review group) and approved by the Manager of Clinton Power Station. The Technical Specification BASES Section, as currently written, requires this determination and approval to be made by the Nuclear Review and Audit Group (offsite review group).
The NRC staff has reviewed your proposed change and determined it is consistent with practices implemented at other BWRs and that performance of this function is in keeping with the duties and responsibilities of the Facility Review Group. We have accordingly revised Section 3/4.7.4 (page B 3/4 7-2) of the Clinton Technical Specification BASES. A copy of.this revised page is enclosed.
Sincerely, i
Original Signed by/
l Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects inclosure: As stated cc:
See next page
(*See Previous Concurrence)
MEB PDIII-2 PDIII-2:PM PD)
D
- HShaw LLuther
- BSiegel:bj.
DMb 8/ /87 8/p/87 8/ /87 8 jy /8 8708190170 370813 PDR ADOCK 05000461 P
4 1
DISTRIBUTION Docket No.: 50-461 Docket File HShaw NRC & Local PDRs PDIII-2 flant File PDIII-2 Rdg. File ACRS(10)
Mr. Frank A. Spangenberg GHolahan Manager - Licensing and Safety M0'Brien Clinton Power Station BSiegel l
P. O. Bex 678 OGC-Bethesda l
Mail Code V920 EJordan I
Clinton, Illinois 61727 JPartlow
Dear Mr. Spangenberg:
SUBJECT:
CHANGE TO BASES SECTION 3/4.7.4 0F CLINTON TECHNICAL SPECIFICATIONS By letter dated July 15, 1987, Illinois Power Company submitted a proposed change to the Technical Specification appended to Facility Operating License No. NPF-62 for Clinton Power Station. The proposed changes would modify Bases Section 3/4.7.4 of the Technical Specification to permit the accessibility of each snubber to be determined by the Facility Review Group (onsite review group) and approved by the Manager of Clinton Power Station. The Technical Specification Bases Section, as currently written require this determination 1
and approval to be made by the Nuclear Review and Audit Group (offsite review 1
group).
The NRC staff has reviewed your proposed change and determined it is consistent with practices implemented at other BWRs and that performance of 1
this function is in keeping with the duties and responsibilities of the Facility Review Group. We have accordingly revised Section 3/4.7.4 (page B 3/4 7-2) of the Clinton Technical Specification Bases. A copy of this revised page is enclosed.
Sincerely, 1
I Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
As stated cc:
See next page l
l
- SeePreviousConcu[rence MEB PDIII-2M PDIII-2:P PDIII-2:PD PDIII-2 HShaw LLuther BSiegel:b DMuller AWang ABw 8/ /87 8/o.}/87 8/// /87 8/
/87 8/ 3 /87 j
I Clinton Power Station Mr. Frank A. Spangenberg Unit I Illinois Power Company cc:
Mr. L. Larson Project Manager General Electric Company Mr. D. P. Hall 175 Curtner Avenue, N/C 395 Vice President San Jose, California 95125 Clinton Power Station P. O. Box.678 Regional Administrator, Region III Clinton, Illinois, 61727 799 Roosevelt Road Glen Ellyn, Illinois 60137
' )
Mr. Wilfred Connell Manager-Nuclear Station Engineering Opt.
Chairman of Dewitt County Clinton Power Station c/o County Clerk's Office P. O. Box 678 DeWitt County Courthouse Clinton, Illinois 61727 Clinton, Illinois 61727 Sheldon Zabel, Esquire Illinois Department Schiff, Hardin & Waite of Nuclear Safety 7200 Sears Tower Division of Engineering 233 Wacker Drive 1035 Outer Park Drive, 5th Floor Chicago, Illinois 60606 Springfield, Illinois, 62704 Resident Inspector Mr. Donald Schopfer U. S. Nuclear Regulatory Commission RR 3, Box 229 A Project Manager Clinton, Illinois 61727 Sargent & Lundy' Engineers 55 East Monroe Street i
Chicago, Illinois 60603 4
i I
i I
l l
I l
i '
s if l I
l
I.
j PLANT SYSTEMS I
l BASES 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM (Continued)
The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required.
Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown.
The pump discharge piping is main-tained fbil to prevent water hammer damage.
3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is mair.tained during and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location, size and system affected shall be available at the plant.
The accessibility of each snubber shall be determined and reviewed by the Facility Review Group and approved by the Manager, Clinton Power Station.
The determination shall be based upon the accessibility of the snubber during plant operations (e.g.,
radiation level, temperature, atmosphere, location, etc.).
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
1 When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to deter-l mine if any safety-related component or system has been adversely affected by l
i l
the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a signifio nt effect or degradation on the supported component or system.
To provide further assurance of snubber reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
Observed failures of these sample snubbers will require functional testing of additional units.
)
l Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
l The service life of a snubber is evaluated via manufacturer input and informa-tion through consideration of the snubber service conditions and associated installation and maintenance records, i.e., newly installed snubber, seal re-placed, spring replaced, in high radiation area, in hign temperature area.
CLINTON - tMIT 1 B 3/4 7-2 Aevision L i
1 1