ML19309F493
| ML19309F493 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/22/1980 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19309F494 | List: |
| References | |
| NUDOCS 8004290502 | |
| Download: ML19309F493 (4) | |
Text
.
[O'N Commonwealth Edison I
./ ons First National Plaza. Chictgo Ilknois
( C
- Address R; ply to: Post Offic:a Box 767 8004290 $ g g
(
Chicago, minois 60690 P
April 22, 1980 f
Mr. Harold R.
Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission i
Washington, DC 20555
Subject:
Zion Station Units 1 and 2 Proposed Change to Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304
Dear Mr. Denton:
Pursusnt to 10 CFR 50.59, Commonwealth Edison Company hereby requests a change to Facility Operating License Nos. DPR-39 and OPR-48, Appendix A, Technical Specifications.
The purpose of this amendment is:
to eliminate references to part length rods, atmospheric relief valves and AEC; to revise the Re tor Protection System Permissive Testing Table 4.1-1; and to provide Quadrant Power Tilt Syntax changes, organization changes, typographical errors, ECCS flow updates, RHR system addition and Low Power Physics Testing restriction.
ihe technical specification revisions and bases are included in Attachment 1 and the proposed changes to the Zion Station Technical Specifications are included in Attachment 2.
Additional information concerning these changes follows.
i The utilizstion of part length rods was prohibited by Amendment No. 20 to DPR-39 and Amendment No. 17 to OPR-48 on May 12, 1976.
As a result of this prohibition, modifications were made to both units removing the part length rods.
Thus, all references to these rods should be deleted from the Zion Technical Specifications.
Similar updating is required regarding atmospheric relief valves which were previously removed from the Zion Technical Specifications in Amendment Nos. 17 and 14.
In addition, the term AEC has been replaced by NRC and numerous typographical errors have been corrected.
With regard to the reactor protection system, permissives are calibrated and functionally tested per the schedule set forth in Table 4.1-1 of the Zion Technical Specifications.
However, these permissives are not instrument channels that can be independently calibrated.
Rather, they are signals or oute its from devices e
N-l
Commonw3alth Edison 5
Mr. Harolo R. Denton, Director April 22, 1980 Page 2 associated with the nuclear instrumentation or turbine first stage pressure channels.
The devices which establish permissive setpoints are listed in Table 3.1-2 of the specification, whereas calibration frequency or applicability of the associated channels is specified in Table 4.1-1.
To eliminate the discrepancy between the channel and permissive device calibration and test frequencies, the permissive schedule has been revised to conform to the channel schedule.
A change to the Zion Technical Specifications is required to clairfy use of the term " Quadrant Power Tilt".
This term is defined in Section 1.0 and the revisions are necessary to maintain consistency in the use of the term throughout the sepcifications.
A revision to the definition is also required to preclude calculation of a tilt using power rangc detector data whenever one channel is inoperable.
Specification 3.2.2.C.2 states that incore thermocouple data is used to determine quadrant power tilt in this situation.
The station and corporate organization charts (Figures 6.1.1 and 6.1.2) have been deleted and the corresponding paragraphs of Section 6.0 have been revised to conform to the existing station organization where three (3) assistant superintendent titles are used, and to the existing corporate organization where all nuclear operations were consolidated under a single vice president.
Section 1
6.0 of the Zion Station Technical Specifications will continue to reference these figures (Figure 1-6 and Figure A) as they are delineated in the Commonwealth Edison Topical Report No. CE-1-A,
" Commonwealth Edison Company Quality Assurance Program for Nuclear Generating Stations".
The purpose of this change is to eliminate the duplication of information in the Technical Specifications and the QA Manual and thereby avoid inconsistencies among Commonwealth Edison's six nuclear stations.
In order to maintain consistency, all six Commonwealth Edison nuclear stations have standardized their station organizations to conform to the Commonwealth Edison QA manual.
This has the advantages of maintaining consistency among the six stations as well as significantly reducing both the Commonwealth Edison and NRC review process when future organizational changes occur.
In lieu of six separate reviews, only one review becomes necessary.
A single review reduces the likelihood of the six Commonwealth Edison stations having.different organization charts at any given time due to single docket review priorities.
Finally, since changes to the QA manual require NRC l
approval, the NRC Staff will still retain authority in this area.
I l
l
3 CommonweCith Edison Mr. Harold R. Denton, Director April 22, 1980 Page 3 Specificati n 4.8.4.B establishes minimum charging pump and safety injection pump cold leg injection flows as required to satisfy the assumptions in ECCS/LOCA analyses.
The proposed changes conform to the minimum ECCS pump flows used in th current ECCS/LOCA analys1.s previously approved in Amendment Nos. 42 and 39.
The proposed changes were inadvertantly omitted from these amendments.
Through an oversight two motor operated suction valves were inadvertently left off Table 4.8.3 which defines the necessary operable equipment for the RHR system to provide its intended safety function.
The proposed change corrects this oversight.
Finally, Amendment Nos. 47 and 44 to the Zion Technical Specifications removed the requirement to perform rod drop testing after maintenance or refueling outages prior to leaving the cold shutdown mode of operation.
During the discussion of that amendment request the NRC Staff indicated that Specification 3.2.1.C.1 was ambiguous on precluding low power physics tests unless the reactor i
coolant temperature was above 5000F.
Both the Staff and l
Commonwealth Edison agreed to the intent of that specification and that it should be revised in a subsequent submittal to ensure that criticality will not occur until above 5000F.
The proposed change clarifies this point.
The proposed changes have been reviewed by On-Site and Off-Site Review with the conclusion that there are no unreviewed safety questions.
Pursuant to 10 CFR 170, Commonwealth Edison has determined that this proposed amendment is a combined Class I and Class II amendment.
As such, Commonwealth Edison has enclosed a fee remittance in the amount of $1,600.00 for this proposed amendment.
The basis for this determination is that the proposed changes are.
administrative in nature and do not have any safety or environmental significance.
Please address any questions that you may have concerning this matter to this office.
L
(
p Commonwe:lth Edison 1
Mr. Harold R. Denton
)
April 22, 1980 l
Page 4 Three.(3) signed originals and thirty-seven (37) copies of 1
l this letter.are provided for your use.
Very truly yours, h
Vy 1
D. L.
Peoples l.
Director of Nuclear Licensing LP:WFN: rap attachments (2) enclosure SUdSCRIBED and S Q N to before th{s ad day of h1F 1980 M fil
]_ N,0 d Q LAkt4%
tary Public
()
i I
3237A l
l 4
1 f
t 1
(
i
=
, _... _,,..,.. - - -.. - -.. - -.