ML19274D052
| ML19274D052 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/22/1978 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901090258 | |
| Download: ML19274D052 (6) | |
Text
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Commonwealth Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 December 22, 1978 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission.
Washington, D.C.
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:
Pursuant to 10 CFR 50.59, Commonwealth Edison Coupany hereby requests a change to Facility Operating License Nos. DPR-39 and DPR-48, Appendix A, Technical Specifications.
The purpose of this amendment is to remove surveil' lance requirements for a number of valves physically removed from the system due to plant modifi-cations and to correct a typographical error.
The proposed change to the Zion Station Technical Specifications is enclosed as Attach-ment I.
The chemical addition valves (OFCV-CA10A,10B, llA, and 11B of Table 4.4-2) were removed as part of the conversion to all volatile treatment of the secondary water.
These valves have been placed out of servica permanently and surveillance is r.st possible.
The valves FCV-SS06 and 0FCV-SS31 in Table 4.9-3 are permanently out of service as a result of changes made to the plant's sampling systems.
These valves were capped off with modification changes and surveillance is no longer necessary.
Valve VC-8481 A and B in Table 4.9-3 should be changed to VC-8480 A and B to correct a previous typographical error.
The above 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 han 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 79010So>st
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NRC Docket Nos.50-295 50-3084 Mr. liarold R. Denton Deccmber 22, 1978 this detemination is that the proposed changes are administrative in nature and do not have any safety or environmental significance.
Three (3) signed originals and thirty-seven (37) copies of this letter are provided for your use.
Very tmly yours, C.R_J Cordell Reed Assistant Vice President Enclosures SUBSCRIBED and Sh0 to before me this c#L{ day of % v i t (s h i t,198.
$$ n ir PII [l]
Ol'Cifo4 Ndtary Public
()
4 4
Commonwealth Edison ZION STATION UNITS 1 AND 2 NRC DOCKET NOS. 50-295 AND 50-304 ATTACINENT I PROPOSED TECHNICAL SPECIFICATION CHANGES The following pages have been revised:
140 205 206
Continuity Check to Final Device Actuation Actuating Device G)
Service Water Pump Starts and System Isolation (Cont'd)
Component OMOV-SW0005 X
OMOV-SWOOO8 X
OFCV-SW54 X
Service Water Pump lc (2C)
X MOV-SWOOO2 X
MOV-S00ll5 X
OMOV-SWOOO7 X
OMOV-SWOOlO X
OMOV-SWOOO9 X
11)
Containment Isolation Phase "A" & Isolation Valve Seal Water Component AOV-VC8149A X
AOV VC8152 X
AOV-DT9159A A
AOV-DT9160A X
AOV-DT9157 X
LCV-DT1003 X
Reactor Coolant Drain Pump 1A (2A) X Reactor Coolant Drain Pump 1B (2B) X FCV-SS9354A X
FCV-SS9355A X
FCV-SS9356A X
FCV-SS9357A X
X FCV-1A01A FCV-PR24A X
FCV-FP08 X
FCV-SSO2 X
FCV-SSO3 X
FCV-SSO4 X
FCV-SS05 X
ACV-VC8149C X
Engineered Safeguards Equipment Actuation Test 140 TABEL 4.4-2 (Sheet 4 of 8)
Valve Service valve Service MOV-VC8100 R.C.
pump seal water return AOV-BD0001 Blowdown from steam generator (double disc)
& FCV-BD17 MOV-CC9414 Cooling water return from R.C.
AOV-BD0002 Blowdown from steam generator (double disc) pumps
& FCV-BD17 MOV-CC9413 A&B Cool'.nq water supply to R.C.
AOV-3D0003 Blowdown frore steam generator pumps
& FCV-BD17 AOV-CC9437 Cooling water return from ex-AOV-BD0004 Blowdown from steam generator cess letdown heat exchanger
& FCV-BD17 CC9500 Cooling water supply to excess AOV-BD0005 Blowdcwn from steam generator letdown heat exchanger
& FCV-BD17 MOV-CC9438 &
Cooling water return from ex-AOV-BD0006 Blowdown from steam generator FCV685 cess letdown heat exchanger
& FCV-BD17 FCV-FP08 Fire protection to containment AOV-BD0007 Blowdown from steam generator
& FCV-BD17 CS0052 &
Containment pressure sensor AOV-BD0008 Blowdown from steam generator CS0053 inlet
& FCV-BD17 CS0054 &
Containment pressure sensor FCV-SSO2 Blowdown from steam generator CS0055 inlet sample CS0056 &
Containment pressure sensor FCV-SS03 Blowdown from steam generator CS0057 inlet sample i
CS0058 &
Containment pressure sensor CS0059 inlet Containment Isolation Valves TABLE 4.9-3 205
A 41
.O Valve Service Valve Service CV-SSO4 Blowdown from steam generator A0V-VC8152 &
Letdown to regenerative heat samole VC8153 exchanger CV-SS05 Blowdown from steam generator SF8787 &
Purification pump to refueling sample SFOO10 cavity CV-WD17 A & B Discharge from containment SF8767 &
Refueling cavity drain OSF0011(Unit 1) sump numps OSFOO12(Unit 2)
C8369A &
R.C. seal water supply FCV-VNO2 A & B Non-filtered ver.ts from containment VC8372A C8369B &
R.C. seal water supply FCV-VF01 A&B Filtered vents from containment VC8372B FCV-PR19 A & B Reactor vessel leak detection C8369C &
R.C. seal water supply VC8372C FCV-PR20 A & B Reactor vessel leak detection
'C8369D &
R.C. seal water supply FCV-PR21 A&B Reactor vessel leak detection VC8372D FCV-PR22 A & B Reactor vessel leak detection
.OV-RC8025 &
Pressurizer relief tank to RC8026 waste gas analyzer FCV-PR23 A & B Reactor vessel leak detection reference sOV-RC8028 &
Primary water to press. relief FCV-PR24 A & B Containment air narticulate & gas RC8029 tank monitor inlet sOV-RC8024 &
Nitrogen canifold to press.
relief tank PR0029 &
Containment air particulate & gas RC8033 PR0030 monitor outlet
'C8480 A & B R.C. loop fill header PR0007 &
Containment air sanpling inlet
- OV-VC8105 &
Charging to regenerative heat PR0008
.VC8106 exchanger Containment Isolation Valves TABLE 4.9-3 (Cont.)
206