ML18081B002
| ML18081B002 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/25/1980 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18081B000 | List: |
| References | |
| NUDOCS 8002040567 | |
| Download: ML18081B002 (8) | |
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PROPOSED CHANGE SECONDARY WATER CHEMISTRY SALEM UNIT NO. 1 TECHNICAL SPECIFICATIONS Description of Change This change deletes all references to secondary water chemistry specifications in the Technical Specifications.
The Operating License will be modified to commitment to a secondary water chemistry program which will not be a part of the O.L. but which contains specific elements as re-quested by the*NRC.
Reason for Change This change is being made at the direction of the NRC -
Reference letter of August 1, 1979, A. Schwencer to F.. P. Librizzi.
Safety Evaluation This change does not affect the present program for second-ary water chemistry and is rather a change in the program administration.
This change has the concurrence of the NRC.
r TO BE INSERTED INTO THE SALEM GENERATING STATION OPERATING LICENSE DPR-70 lfCONOARY W1'TER CHEMISTRY MONITORING ttte* licensee shall implement a secondary water chemistry :.oni~o~ing
- program to 1 nhi bit steam genera tor tube degradation. ':h1 s ;irogr!.rn shall include:
- 1. Identification of a sampling schedule for the critical para=::eters and control points for these parametersi t-. -*l~entifica.tion of the procedures used to quantify ;:ararr.et!!rS that are crftical to control points;
.!;-* fdentification of process sampling points;
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- Y>rocedure for the recording and management of data;
.s.. **Procedures defining corrective actions for off ccntrc1 :>oin:
dlenistr)' conditions; and
- i. A procedure identifying the authority responsibie ~or t:.e ir.ter-pretation of the data, and the sequence and timir:g of a:Jn~nistra:ive events required to initiate corrective action.
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..................................
3/4 6-1 Containment Leakage.Gcoooooooooooooooo*****oo***o***P**
3/4 6-2 Containment Air Locks..................................
3/4 6-5 Air Temperature ****** ooo*****oo**oooo~o***oo*o*********
3/4 6-7 Containment Structural Integrity.......................
3/4 6-8 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.*.*.******* ~******************
3/4 6-9 Spray Additive System..................................
3/4 6-iO Containment Cooling System.............................
3/4 6-11 3/4.6.3 CONTAINMENT ISOLATION VALVES *.**.*.***.****************. *
- 3/4 6-12 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers. * *. *. * * * * * * *. *. * * *. * * *. * * * *. * *.. *..
- 3/ 4 6-18 Electric Hydrogen Recombiners..........................
3/4 6-19 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Val ve s..*.. o ********* o ~ **** o ********* o * * * * * * * * *
- 3 I 4 7 -1 Auxiliary Feedwater System.............................
3/4 7-5 Auxiliary Feed Storage Tank............................
3/4 7-7 Act i vi ty.. ID
- ***** o o ** Cl ***** o
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- 3 / 4 7 -8 Main Steam Line Isolation Valves.......................
3/4 7-10 Secondal) We:ter Ghem;!try.. DOOGO**o*o*.**o**************
3/4 7 11 SALEM - UNIT l VI c
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DITION FOR*OPERATION APPLICABILITY:
ACTION:
condary water chemistry shall
. 7-3.,-
2 and 3.
(To be detennined in a er set forth in th ases in approximately six months and to be impo by a change to s Specification.)
SURVEILLANCE RE UIREMENTS 4.7.1.6 The secondary water. hemistry sn 1 be determined to be within the limits by analysis of se parameters t the frequencies specified in Table 4.7-3.
3/4 7-11
Water Sample
. Location Condenser Condensate Steam Generator Slowdown TABLE 3.7-3 SECONDARY WATER CHEMISTRY CONTROL PARAMETERS Total Cation Conductivity umhos/cm2 @ 25°C Limits pH @25°C Limits N.A.
Free Hydroxide ppm CaC03 limits Limits to be es ta.....,._,..,, in approximately 6 months based upon test p in bases.
N.A.
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w Condenser Condensate Steam Generator Blowdown TABLE 4.7-3 SECONDARY WATER CHEMISTRY SURVEILLANCE REQUIREMENTS pH @ 25°C Frequency Free Hydroxide ppm CaCO Fr N.A.
urveillance frequencies to be established in approxim~tely 6 months based ujj:p""'llllli~
described in bases.
Frequency N.A.
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PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a s~all fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the"steam generator of the affected steam line. These values are consistent ~ith the assumptions used in the accident analyses.
3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to l) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2} limit the pressure rise within containment in the event the steam line rupture occurs within contain-ment.
The OPERABILITY of the.main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
SALEM - UNIT l B 3/4 7-3
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PlANT SYSTEMS BASES RY WATER CHEMISTRY Continued The tes include an analysis of the of the river water oint of intake for the S clear Generating Station. The analysis s tify the va-r*
- aces of ions which upon concentration may have the inducement for stress corrosion in the steam generator test program shall also evaluate the efficiency of er treatmen s in the Salem facility for removal ions and the potentia ition of other ions re rom the treatment method.
The test shall analyze ration phenomena and the concentration rates in and the secondary water system and shall consider concentra he recirculating cooling water system" 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70°F and 200 psig are based on average steam generator impact values taken at l0°F and are sufficient to prevent brittle.fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundan.t cooling capacity of this system, assuming a single failuret is consistent with the assumptions used in the accident conditions within acceptable limits.
SALEM - UNIT 1 B 3/4 7-4
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