ML19341C454
| ML19341C454 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/17/1981 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19341C455 | List: |
| References | |
| TASK-1.A.1.1 NUDOCS 8103030540 | |
| Download: ML19341C454 (4) | |
Text
.
s Conwnonw chh Edison
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) one First Natu)nal Plaza. Chicago, llknojs C7 Address Reply to: Post Office Box 767 Chicago, Illinois 6%90 i
s February 17, 198
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Mr. Harold R. Denton, Director g.
Office of Nuclear Reactor Regulation
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U.S.
Nuclear Regulatory Commission 2
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Washington, DC 20555 Sgj (( j c)
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Subject:
Zion Station Units 1 and 2 Proposed Amendment to Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304 4
i References (a):
July 2, 1980, letter from D.
G. Eisenhut j
to All PWR Licensees.
(b):
December 11, 1980, letter from T. R.
Tramm to H.
R. Denton.
s 4
Dear Mr. Denton:
Pursuant to Reference (a) and the requirements of 10 CFR 50.90, Commonwealth Edison Company hereby requests changes to Facility Operating License Nos. DPR-39 and DPR-48 and Appendix A, Technical Specifications.
The purpose of this amendment is to incorporate requirements for continued implementation of TMI-2 Lessons Learned Category "A"
items.
The proposed technical specifications cover the following areas as specified in Reference (a):
1.
Emergency Power Supply Requirements 2.
Valve Position Indication 3.
Instrumentation for Inadequate Core Cooling 4.
Containment Isolation 5.
Auxiliary Feedwater Systems 6.
Shift Technical Advisor to this letter indicates the manner in which each of these areas is being addressed. to this letter contains the proposed changes and a list which specifies the changes on each page.
l 18103030545 9
. Reference (a) also proposed wording for additional license conditions regarding a System Integrity Measurements Program and Improved Iodine Measurements capability.
That wording is satisfacorty and is reproduced verbatim in Attachment 3 to this letter.
These changes have been reviewed and approved by Commonwealth Edison's On-Site and Off-Site Review with the conclusion that there are no unreviewed safety questions.
The wording is consistent with that of other proposed enanges that have not yet been approved by the NRC.
In particular, pages 300, 301, 302, 302a and 303 are the same versions as were included in our letter of April 22, 1980 but have been retyped.
No fee is being submitted for this proposed amendment.
Reference (a) indicated that this amendment is in the puolic interest and is exempt from fee per 170.11.
Please address any questions that you may have concerning this matter to this office.
Three (3) signed originals and thirty-seven (37) copies of this letter are being provided.
Very truly yours, fe T.
R.
Tramm Nuclear Licensing Administrator Pressurized Water Reactors Attachments cc:
Resident Office - Zion SUBSCRIBED and SWORN to before mg this
/h/?W day of Vr/1<<
, 1981 i
Notary'Public 05738
ATTACHMENT 1 Zion Station Units 1 and 2 NRC 00cket Nos. 50-295 and 50-304 Explanation of Proposed Technical Specifications 1.
EMERGENCY POWER SUPPLY REQUIREMENTS (NUREG-0578, Section 2.1.1)
This section considers the emergency power supply requirements for 1) Pressurizer heaters, 2) Pressurizer power operated relief valves (PORV) and block valves, and 3) Pressurizer level indicators.
Zion Technical Specifications presently have requirements for the pressurizer and PORV to be operable.
The technical specification for the pressurizer has been upgraded to include requirements for 150KW of heaters to be operable and that a maximum water level not be exceeded.
The requirement for 150KW of heaters provides for the ability to initiate and maintain natural circulation.
The PORV technical specification change requires that the PORV and block valves be operable in Modes 1, 2, and 3 (Power operation to Hot Shutdown, with Ta vg greater than 3500F).
Requirements for level indicators and position indicators are proposed in this technical specifications change.
The change ruquires the inoicators to be operable and identifies the indicators in Table 3.8.9-1,
" Accident Monitoring Instrumentation."
2.
DIRECT INDICATION OF VALVE POSITION (NUREG-0578, Section 2.1.3a)
This section considers direct measures for determining PORV and safety valve positions.
Direct indication provides assurance that the integrity of the reactor coolant pressure boundary is maintained and that the loss of integrity can be diagnosed.
The proposed technical specification change provides for the operability of direct indication of the PORV, PORV block valves i
and pressurizer safety valves in Ta ble 3. 8. 9-1,
" Accident l
Monitoring Instrumentation."
3.
INfTRUMENTATION FOR INADEQUATE CORE COOLING (NUREG-0578, Section i
2.
3b)
Our response to the requirements of this section of the NUREG 1
was the installation of a subcooling meter.
The proposed technical specifications includes the requirement for the calculation of the subcooling margin in Table 3.8.9-1, " Accident l
Monitoring Instrumentation."
. 4.
DIVERSE CONTAINMENT ISOLATION (NUREG-0578, Section 2.1.4)
This section considers diverse methods by which effective Co.P:ainment isolation is accomplished and maintained.
Initiation of containment isolation solely on containment pressure rise is inadequate.
We previously indicated that the existing containment isolation system already includes diverse signals for actuation.
Zion Technical Specification 3.4 presently address diverse containment isolation actuations.
5.
AUTO INITIATION OF AUXILIARY FEED (NUREG-0578, Section 2.1.7a)
This section discusses the automatic initiation of the Auxiliary Feedwater System (AFWS).
The proposed technical specification includes the AFWS in Table 3.4-1,
" Engineered Safeguards Actuation System - Limiting Conditions For Operation and Setpoints"; Table 3.4-2, " Engineered Safeguards Instrumentation Numbers"; and Table 4.4-1,
" Engineered Safeguards Systems Testing and Calibration Requirements."
This proposed change establishes the limiting conditions for operation for automatic initiation of the AFWS instrumentation and control.
6.
AbyILIARY FEED FLOW INDICATION (NUREG-0578, Section 2.1.7b)
This section again discusses indicators as was done in Item 2 above (Section 2.1.3.a).
The indication requirements for auxiliary feedwater flow to the steam generators has been included in the proposed technical speci fications in Table 3.8.9-1,
" Accident Monitoring Instrumentation."
i' 7.
SHIFT TECHNICAL ADVISOR (NUREG-0578, Section 2.2.lb)
The proposed technical specification change included the rec.uirement for the Shif t Technical Advisor (STA) in Section 6.1.D and aods this person to the shift manning table, Table l
6.1.3.
Zion Station presently conforms to an interim criteria for shift staffing as stated in the response to Reference 3.
Since it is not anticipated that the full requirements for the STA will be met before June 1, 1981, a footnote for Section 6.1.0 states that the change will not take affect before June 1, l
1981.