ML20210K355
| ML20210K355 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/01/1997 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20210K322 | List: |
| References | |
| 7.8.1, NUDOCS 9708190235 | |
| Download: ML20210K355 (42) | |
Text
_
WMNMM RTYPE H6.07 WORKING COPY JUL 011997 PILGRIM NUCLEAR POWER STATION som y gy'*
Procedure No. 7.8.1 nr,xTIErwr.ca WATER QUALITY LIMITS REQUIRED REVIEWS REVIEWERS AND APPROVERS Stop
$ A &
(s b c / n
[]*g*h
[j"h Think S
R Act Technical Reviewer
' Date
)y) hw 2 s - sous - 17 4
Review vasator u Date c o J u. A e/u/n
~
MSTP RELATED Procedure Owner
'Date N/A SAFETY REVIEW REQUIRED QAD Manager Date ORC REVIEW REQUIRED pp g c/yetgg O
Chair p
Date
[U 7Qo 7///97 anager
/Ddte /
j
{
Effective Date:
'7 d/
7 "8"*%88M 858886 PDR-070026 7.8.1 Rev.16
?
REVISION LOG REVISION 16 Date Originated 6/96 Paaes Affected Description
-6 in References add PNPS TP96-048, TM 96-20, and GE document
- to Fuel Warranty Operating Limits and delete Water Quality GE document and update BWR Water Chemistry Guidelines.
6,7,18,20 Delete active reference to Nuclear Organization Policy C.1.05 which is retired, incorporate elements of retired Policy C.1.05.
7-9 Replace " Start /Sby" with "Stadt & Hot Siby" 7,8,10,11,18,27-Update organization titles due to reorganization.
9 Update referenced EPRI document #.
10,11,27 Revise values for Action Levels to agree with new EPRI guidance.
15,24 Delete reference to ECP "of 304SS in Recirc Water" as different probes / locations may be utilized to determine ECP.
21-26 Replace " Normal" and " Maximum" with " Continuous" and update GE Fuel Warranty values; revise Notes.
22-24 Add Reactor water zine as a control parameter to support TM 96-20.
24,28 Raise achievable value of silica from 100 ppb to 150 ppb in both Reactor water and Reactor water cleanup systems.
25 Change feedwater conductivity value prior to startup from 0.07 to
< 0.065 S/cm.
26 Change feedwater dissolved O Action Level i requirement from 2
< 20 to < 15 ppb.
26,27 Add feedwater zinc as a control parameter to support TM 96-20.
-28 Major rewrite to mirror new EPRI guidelines.
29,30 Revise silica Achievable Value for CSTs and TWTs to s 20 ppb to reflect change in new EPRI guidelines.
32 Change Rx water oxygen parameter frequency to be " control" rather than " diagnostic".
37' Revisa Reactor water (primary coolant) table to reflect changes to rest of Procedure.
7.8.1 Rev.16 Page 2 of 38
REVISION LOG (Continued)
REVISION 15 Date Originated 12/94 Paoes Affected Descriotion 20 Clarify daily sampling during shutdown requirement.
24 Change EPRI action level to 15 ppb for feedwater and add condensate dissolved oxygen.
26 Reduce Achievable Value for total organic carbon in fuel pool. Add frequency Note for Fuel Pool.
27 increase Achievable Value for silica in Condensate Storage Tanks, Makeup Demineralizers, and Treated Water Tanks bued on cost benefits at the direction of Chemistry Division Manager.
27 Add Achievable Value for TWT total organic carbon during outages based on cost benefits at the direction of Chemistry Division Manager.
27 Change upper pH Achievable Value for CCW to 9.4.
7.8.1 Rev.16 Page 3 of 38
l 9
l l
TABLE OF CONTENTS L.
l East 1.0 P U RP O S E AN D S C O P E.................................................................................. 6
2.0 REFERENCES
6 3.0 D E F I N IT I O N S................................................................................................... 7 3.1 AC H IEVAB LE VALU E (PN P S).............................................................. 8 3.2 EPRI BWR OWNERS GROUP DEFINITIONS.......................................
9 4.0 DlSCUSSION...................................................................................................12 4.1 IMPORTANCE OF WATER CHEMISTRY CONTROL..........................
12 4.2 DEFINITIONS OF CONTROL AND DIAGNOSTIC PARAMETERS...... 13 4.3 CONDENSATE AND FEEDWATER SYSTEMS....................................
17 4.4 REACTOR SHUTDOWN - RESIDUAL HEAT REMOVAL
( R H R ) SYST E M..................................................................................
17 5.0 S P ECIAL TOOLS AN D EQ UIPMENT............................................................
17 6.0 PRECAUTIO N S AN D LIMITATIO N S.............................................................. 18 7.0 P RE R E Q U I S ITE S........................................................................................
1 8 8.0 PROCEDURE.................................................................................................19 8.1 R EACTO R WATE R.'.............................................................................. 21 8.2 REACTOR FEEDWATER/ CONDENSATE......................................... 25 8.3 CONTROL ROD DRIVE (CRD)/ CONDENSATE DEMINERAllZER
- E F F L U E NT ( C D E )............................................................................... 27 8.4 MIS C E LLAN EO U S SYST EM S............................................................. 2 8 9.0 AC C E PTAN C E C R ITE RI A............................................................................ 30 7.8.1 Rev.16 Page 4 of 38 i-'
TABLE OF CONTENTS (Continu;d)
P_!uut 10.0 ATTAC H M E NT S.............................................................................................. 3 0 ATTACHMENT 1 - EPRI RECOMMENDATIONS FOR CONTINUOUS PROCESS INSTRUMENTATION (TABLE).................................. 31 ATTACHMENT 2 -EPRI RECOMMENDED SAMPLING AND ANALYSIS FREQUENCY FOR CONTROL AND DIAGNOSTIC PARAMETERS DURING POWER OPERATION (TABLE)...........
32 ATTACHMENT 3 -CONDUCTIVITY / CONCENTRATION RELATION FOP. VARIOUS CHEMICALS (TAB LE)........................................ 33 ATTACHMENT 4 -VARIATION IN CONDUCTIVITY OF CHLORIDE AND SULFATE SOLUTIONS AT 25'C (GRAPH).........................
34 ATTACHMENT 5 - MAXIMUM POSSIBLE CHLORIDE CONCENTRATION FOR ANY GIVEN CONDUCTIVITY FOR COMMON C HLORID E COMPOU N DS (GRAPH).......................................... 35 ATTACHMENT 6 - RESTRICTIONS IMPOSED BY THE CONDUCTIVITY /pH RELATION (GRAPH)................................. 36 ATTACHMENT 7 - REACTOR WATER QUALITY LIMITS FOR VARIOUS P LANT C O N D ITI O N S................................................................. 37 ATTACHMENT 8 -IDENTIFYING CHEMISTRY EXCURSIONS (TABLE)..................
38 7.8.1 Rev.16 Page 5 of 38
1.0 PURPOSE AND SCOPE This Procedure provides PNPS's water quality chemistry (and radiochemistry) limits for various plant operating conditions. It addresses Control Limits required by Technical Specifications, EPRI BWROG Water Chemistry Guidelines, and the GE Fuel Warranty, as well as Achievable Values as determined by Boston Edison Company review of pertinent sources. IDR 2036]
2.0 REFERENCES
[1]
BECo Admin!strative L!mits
[2]
BWR Water Chemistry Guidelines (EPRI TR-103515-R1),1996 Revision
[3]
BWR Water Chemistry Guldelines (EPRI TR-103515),1993 Revision
[4]
DR 2036
[5]
Fue Warranty Operoting Limits (GE Document No. 23A4715 Rev 3)
[6)
NOP 92A1,
- Problem Report Program"
[7]
Nuclear Policy No. C.1.05; Water Chemistry Program,1988 (retired)
(0)
PNPS Procedures (a) 1.3.5, " Adherence to the Fuel Warranty Specifications *
(b) 2.4.148, ' Abnormal Reactor Water Chemistry" (c)
TP96-048, 'GEZIP System Zinc Oxide Chemical Addition"
[9]
Technical Specifications Sections (a) 3.6.B (b) 4.6.B
[10]
TM 96-20, Install Temporary Zine injection Skid (GEZIP) s 7.8.1 Rev.16 Page 6 of 38
3.0 DEFINIT 10HE l
This section defines terminology used to comply with regulatory and administrative requirements. Section 3.1 addresses PNPS Achievable Values arid Section 3.2 deals with EPRI Guidelines. The entire Definitions section should be read as a whole in order to understand the interplay between the different sets of limits / values for various systems under changing plant conditions.
[1]
Control Limit (or Limit) - A level, concentratiori, or range established for controlling key parameters that is subject to the following stipulations:
(a)
Relath e to Technical Specifications, that limit which should not be exceeded under any circumstances, otherwise an orderly unit shutdown shall be conducted in accordance with Technical Specifications Section 3.6.B.S.
(b)
Pertaining to EPRI action levels and the GE Fuel Warranty, those limits which should not be intentionally exceeded without permission from senior management. Refer to Section 3.2 for additional definitions.
[2]
Achievable Value - Parameter values which should not be intentionally exceeded without approval of the Chemistry Department Manager (or designee). Refer to l
Section 3.1 for additionalinformation. (DR 2036)
[3]
Plant Condition - Concerning Reactor water quality, refers to the operating status of the unit (mode, coolant temperature, pc,ver level, steaming rate, elapsed time in a given status, etc.). Different control limits are in effect for various plant conditions, which are mutually exclusive. The following terms have been adapted from various sources (primarily Technical Specifications):
(a)
Shutdown - The final part of the power reduction process when taking the unit from the operating condition to either of the following two modes:
Hot Shutdown - Recctor coolant temperature greater than 212'F and mode switch in " Shutdown",
Cold Shutdown - Reactor coolant temperature less than or equal to e
212'F, Reactor Vessel nonpressurized (no steam being generated). Also, termed " cold condition".
(b)
< 100,000 lb/hr (not in effect during the "startup" period) - When the mode switch is in " Start & Hot Stby" AND coolant temperature exceeds 212*F A_N,2 the unit's steaming rate is less than 100,000 pounds / hour (that is, Reactor 51% design power level or 5 20 MWth).
7.8.1 Rev.16 Page 7 of 38 s
__________U
3.0 DEFINITIONS (Continued) l l
(c)
Hot Standby - Mode switch in " Start & Hot Stby", coolant temperature > 212*F, Reactor pressure < 600 psi, and the MSIVs closed. See Definition 3.0[3)(b) for comparision.
(d)
Startup - The period during power ascension from when the mode c/vitch was placed in " Start & Hot Siby" until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the mode switch goes to "Run".
Should a Scram occur while still in the startup condition, any recovery (even immediate) is considered a new startup.
(e)
Power Operation - Mode switch in "Run" (or " Start & Hot Stby"), Reactor power [
above 1% (steaming rate > 100,000 lb/ hour), and more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since startup commenced (see "Startup" definition above). Usually, power operation will be entered 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the mode switch went to "Run".
(f)
Run - Mode switch in "Run" and Reactor pressure > 785 psi, typleally
> 5% power level.
[4]
Normal - Refers to that period when the unit or a particular system is operating under steady state conditions.
[5]
Nonpressurized - Reactor at or below 212'F (100'C).
[6]
HWC - Hydrogen Water Chemistry
[7]
SHE - Standard Hydrogen Electrode 3.1 ACHIEVABLE VALUE (PNPS)
The Achievable Value of a parameter is a target or goal that is used when good engineering judgment indicates that it enhances system (s) reliability / performance and/or when a corresponding EPRI, Technical Specifications, fuel warranty, etc., value is not available.
[1]
Objectives:
(a)
To maintain satisfactory control of plant chemistry and water quality by application of good operating practices.
(b)
To promptly identify, correct, and/or evaluate the cause of an abnormal value.
[2]
Action: When an Achievable Value is reached, perform actions indicated by Procedure or as directed by Chemistry Supervision. Approval of the Chemistry Department Manager (or designee) is required to intentionally exceed Achievable Values.
7.8.1 Rev.16 Page 8 of 38
3.2 EPRI BWR OWNERS GROUP DEFINITIONS EPRI BWR Water Chemistry Guidelines [(EPRI TR-103515 R1) 1996 Revision] defines plant conditions and specific actions associated with out-of specification parameters. Because the criteria used to identify these conditions, and the resultant actions recommended, do not correspond to PNPS Technical Specifications Sections 3.6.B and 4.6.B, they have been modified (in accordance with EPRI guidance) to conform to PNPS Technical Specifications.
3.2.1 Plant Conditions (EPRI)
Refer to Definition 3.0[3] for terminology used in this Procedure to determine plant condition for Reactor water parameters (Section 8.1). For Sections 8.2 and 8.3, Reactor power level is identified instead of plant condition to determine appropriate limits and/or values.
Mode Switch Rx Pwr Average Reactor Mqda Position (s)
Level Coolant Temperature
[1] Cold Shutdown Shutdown or Refuel 0%-
< 100*C (< 212'F)
[2] Startup/ Hot Start & Hot Sby or Run 510%
> 100*C to Operating Standby
_ Temperature
[3]
Power Operation Run
> 10%
Operating Temperature 3.2.2 Action Level 1 The Action Level i value of a parameter represents the limit above which data or engineering judgment indicates that long-term system reliability may be threatened, thereby warranting an improvement of operating practices.
3.2.2.1 Objective To promptly identify and correct the cause of the out-of-normal value without power reduction.
7.8.1 Rev.16 Page 9 of 38
3.2.2.2 Action
[1]
Inform appropriate levels of management of the existence of the condition, the implications, and the possible corrective measures over the short and long terms.
[2]
Return parameter to less than Action Level 1 value within 96 operating hours following confirmation of excursion.
[3]
If the parameter has not been reduced below the Action Level i value within 96 operating hours, a technical evaluation (with formal review by management) should be performed to determine the cause of the problem and action plan (s) should be developed to correct the cause of the problem. Submit a Problem Report to the NWE (if not done already and if still in Action Level 1 for greater than 96 operating hours for the same parameter).
1 3.2.3 Action Level 2 Action Level 2 of a parameter represents a limit above which data or judgment Indicates that significant degradation could be done to the system in the short term, thereby warranting a prompt correction of the abnormal condition.
3.2.3.1 Objective To minimize damage to the Reactor coolant system by limiting the duration of out-of specification chemistry.
3.2.3.2 Action
[1]
Efforts should be made to reduce the parameter below the Action Level 2 limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, immediately notify the Chemistry Department Mancger. Submit a Problem Report to the NWE.
[2]
If the parameter has not been reduced below the Action Level 2 limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an orderly unit shutdown shall be initiated and the plant shall be brought to a cold shutdown as rapidly as operating conditions permit. In some cases, it may be more prudent to continue operation, perhaps at reduced power, if such effort results in minimized exposure of components to elevated parameter concentrations, if such an approach is adopted, an Engineering Evaluation shall be performed. This evaluation is likely to be case and site specific.
[3]
If it is foreseeable that the parameter will be below the Action Level 2 value within the time period required to achieve an orderly shutdown, power operation can be maintained.
[4]
Following a unit shutdown caused by exceeding an Action Level 2 limit, a review of the incident shall be performed and appropriate corrective measures taken before the unit is restarted.
7.8.1 Rev.16 Page 10 of 38
3.2.4 Action Lev:13 The s etion Level 3 value of a parameter represents the limit above which data or engineering
,Sdgment indicates that it is inadvisable to continue to operate the plant.
3.2.4.1 Objective To correct a condition whleh may result in rapid Reactor coolant system damage during a
continued operation.- The purpose is to stop ingress and reduce further concentration of i
harmful impurities. It may be more prudent in some situations, such as a resin ingress scenario, to maintain power operation'f ye effort results in minimized exposure of components to elevated parameter ceflodons. If such an approach is adopted, an Engineering Evaluation shall be perfox.wil pero hand) to document how it is expected to result in soceptable degradation of the Recotor materials. This evaluation is likely to be case and site specific.
3.2.4.2 Action
[1]
An orderly unit shutdown should be initiated immadiately. Immediately notify the Chemistry Department Manager and submit a Problem Report to the NWE.
[2]
Following a unit shutdown caused by exceeding an Action Level 3 limit, a review of the incident should be performed and appropriate corrective measures taken before the unit is restarted.
[3]
Action shall be taken to reduce the parameter to below Action Level 3 value as quickly as possible.
-[4]
Coolant temperature shall be reduced to < 212*F, unless a higher temperature leads to more rapid control of the paiemeter, if it is foreseeable that the parameter will be below the Action Level 2 value within the time period required to achieve < 212'F, power operation can be maintained.
7.8.1 Rev.16 Page 11 of 38
4.0 DISCUSSION 4.1 IMPORTANCE OF WATER CHEMISTRY CONTROL 1
[1]
The importance of establishing and maintaining appropriate water chemistry conditions in the Reactor Coolant System (RCS) of bolling water reactor (BWR) nuclear power plants is well established Most operating BWRs (including PNPS) have experienced unanticipated pipe cracking problems that have resulted in a significant loss of availability and increased the total personnel radiation exposure essociated with inspection and repair. The cause of these problems has been intergranular stress corrosion cracking (IGSCC) and transgranular stress corrosion cracking (TGSCC) which result from the simultaneous occurrence of sp" u - ster environment and material and stress conditions. The two key aspectr. *,spect to the contribution of the water environment to IGSCC and TGSCC, are the e ' Jing power of the water (as reflected by the electrochemical corrosion potential (EL i of stainless steel) and the concentrations of ionic impurities, partiwlarly sulfate anu chloride. Plant data indicate that by injecting hydrogen into the feedwater, the oxidizing power of the Reactor water (and the resultant ECP of stainless steel) can be reduced to a level at which IGSCC cannot be detected if, at the same time, the concentration of lonic impurities in the coolant is maintained at a very low level. This approach to BWR chemistry control is called hydrogen water chemistry (HWC). Information Indicates that controlling both the oxidizing power and the impurity concentration of the Reactor water o.f BWRs can greatly reduce pipo cracking problems without adversely affecting fuel performance or shutdown radiation fields However, the introduction of HWC willincrease radiation fields (especially in the Turbine Building) during operation.
[2]
In addition to reducing IGSCC, research shows that appropriate control of BWR water chemistry will also assist in controlling radiation buildup, minimizing fuel failure, arid minimizing chemistry caused damage to the Turbine.
[3]
The most common sources of impurities that result in increases in Reactor water conductivity are condenser cooling water in-leakage, improper operation of ion exchange units, air in-leakage, and radwaste recycle. In addition to situations of relatively continuous ingress, such as from low level condenser in-leakage, transient events can also be significant. The major sources of impurities during such events are resin intrusions, organic chemical intrusions, inorganic chemical intrusions, and improper rinse of resins.
7.8.1 Rev.16 Page 12 of 38
4.2 DEFINITIONS OF CONTROL AND DIAGNOSTIC PARAMETERS Two categories of water chemistry parameters (control and diagnostic) can be distinguished.
4.2.1 Control Parameters Control parameters are those known to affect corrosion performance of RCS materials, fuel performance, or radiation field buildup and which must be measured and controlled to optimize plant performance, in this Procedure, the control parameters are conductivity, chloride, sulfate, oxygen, iron, copper, and ECP of stainless st6el.
[1]
Conductivity The conductivity is an easily measured indicator of the total concentration of ionic impurities. Increasing levels of rnany lonic impurities adversely influence both the stress corrosion cracking behavior of RCS materials and the rate of radiation field buildup and also can affect fuel performance. Therefore, conductivity levels in the Reactor water should be maintained at the lowest levels practically achievable.
Reactor water conductivities of less than 0.2 pS/cm are achievable in BWRs during power operation and levels below 0.3 pS/cm can be maintained by using good operational practices regardless of the types or capacities of the Reactor Water Cleanup and Condensate Demineralizer Systems.
(2)
Chloride Chlorides are among the most potent promoters of IGSCC of sensitized stainless steels and are also capable of inducing transgranular cracking of nonsensitized stainless steels. Chlorides also promote pitting and crevice attack of most RCS materials.
Chlorides normally are associated with condenser in-leakage, but inputs via radwaste processing systems have also occurred.
Because chloride is implicated in several different corrosion phenomena, its level in Reactor water should be kept as low as practically achievable during power operation.
Values of less than 5 ppb are routinely attainable with good operating practices.
IGSCC will proceed at an increased rate with increasing chloride concentrations between a few ppb and 200 ppb. Above 200 ppb there is an increasing risk of chloride-induced intergranular stress corrosion cracking of annealed stainless steel.
7.8.1 Rev.16 Page 13 of 38 l
1
l l
4.2.1 Control P;rcmet:rs (Continued)
[3]
Sulfate Sulfate has been found to be more aggressive in promoting IGSCC of sensitized Type 304 stainless steel in BWR-type water (in laboratory tests) than any other on, including chloride. Sulfates have also been implicated in environment assisted cracking of high nickel alloys and carbon and low-alloy steels. Sulfate ingress can result from cooling water in-leakage, regenerant chemical in-leakage, or resin ing ess.
Ingress of resins into the RCS has caused more " severe" water chemistry transients than any other impurity source, so sulfate contamination of Reactor water has a relatively high probability of occurrence.
The conductivity limit of 0.3 pS/cm implicitly limits the sulfate level to 89 ppb. Since conductivity control does not limit sulfate to the desired level, the sulfate level has been made a control parameter.
[4]
Oxygen Dissolved oxygen has been identified as a major contributor to IGSCC of sensitized stainless steels and reduction of oxygen content is known to reduce the tendency for pitting and cracks of most other RCS and balance of plant materials.
During power operation, most of the oxygen content of Reactor water'is due to the radiolysis of water in the core and, therefore, oxygen control cannot be achieved through traditional chemistry and operational practices. Oxygen control can be attained through hydrogen injection. Control of Reactor water oxygen during startup/ hot standby may be accomplished by utilizing the deaeration capabilities of the condenser. Independent control of control rod drive (CRD) cooling water oxygen concentration of less than 50 ppb during power operation is desirable to protect against IGSCC of CRD materials.
Carbon steels exhibit minimal general corrosion and release rates in water with a conductivity 5ss than 0.1 pS/cm if the concentration of oxygen is in the rance of 20 to 1000 ppb. - hegulation of Reactor feedwater dissolved oxygen to 20 to 50 ppb during power operation will minimize corrosion of the Condensate and Feedwater System and reduce the possibility of locally increasing Reactor water oxygen concentrations. It is important to note that for oxygen concentrations below 20 ppb the data indicates an increase in the corrosion rate for carbon steels.
7.8.1 Rev.16 Page 14 of 38
l 4.2.1 Control Parameters (Continued) 1
[5]
fron High iron inputs into the Reactor have been associated with excessive fuel deposit buildup. Proper regulation of feedwater purity and dissolved oxygen levels will minimize Iron transport to the Reactor. This, in turn, should minimize fuel deposits and may assist in controlling radiation buildup.
Corrosion product transport to the Reactor during a startup after an extended outage can be reduced by flushing the Condensate /Feedwater System. Recirculation from the hotwell through the condensate polishers and feedwater heater train is an effective technique for accomplishing cleanup.
Feedwater iron values less than or equal to 15 ppb and less than or equal to 2.0 ppb are achievable during startup/ hot standby and power operation, respectively. These values are consistent with good operating practices.
[6]
Copper input of copper to the Reactor has been associated with severe fuel corrosion at several plants. A prestartup flushing program will help reduce copper transport to the Reactor after extended outages. Optimization of condensate polisher equipment performance for copper removal can reduce copper input rates.
[7]
ECP of Stainless Steel The electrochemical corrosion potential (ECP) of a metal is the potential it attains when immersed in a water environment. The ECP is measured by comparison to a standard reference electrode at a temperature as close to the Reactor recirculation water temperature as possible.
At the Action Level 1 values of conductivity, sulfato and chloride, the ECP must be below -0.23V (-230mV) SHE to suppress IGSCC. An achievable value of -0.30V
(-300mV) SHE has been established to provide a reasonable response margin.
7.8.1 Rev.16 Page 15 of 38
4.2.2 Dl: gnostic Parcm:;t:rs Diagnostic parameters include parameters that will help the plant Chemistry staff interpret deviations from the control parameter values. Although some of these parameters may affect corrosion performance of RCS materials, fuel performance, or radiation field buildup, values at which corrective actions should be taken are not given in the EPRI guidelines for these parameters because sufficient data are not available to quantify such values (concentration limits on ionic diagnostic parameters are inferred by conductivity).
Recommended diagnostic parameters for which conventional analytical methodologies are available include fluoride, organics, sodium / cation conductivity, sliica, and pH. Quantifying these parameters will help to identify origins of impurity ingress.
[1]
Fluoride Fluoride promotes many of the same corrosion phenomena as chloride, including IGSCC of sensitized austenitic stainless steels, and may also have the potential to cause corrosion of Zircaloy core components. Fluorides are known to have been introduced into the RCS via the radwaste processing system and have also been observed following welding repairs as a result of incomplete flux removal.
[2]
Organics Organic compounds can be introduced into the RCS via turbine or pump oil leakage, radwaste, or makeup water systems. Of particular concern is the possibility that halogenated organic compounds (e.g., cleaning solvents) may pass through the radweste systems and enter the RCS where they will decompose releasing corrosive halogens (e.g., chlorides and fluorides). The reason for concern is that these halogenated compounds are undetectable by analysis methods such as conductivity or chloride monitoring until they thermally or radiolytically decompose in the RCS.
[3]
Sodium / Cation Conductivity Routine measurement of conductivity, condensate sodium, or cation conductivity levels can provide a means for detecting condenser in-leakage.
Sodium (or Na-24) monitoring of the Reactor water may also be beneficial in identifying Condensate Demineralizer system problems.
7.8.1 Rev.16 Page 16 of 38 5
4.2.2 Diagnostic Pcrcmet:rs (Continued)
[4]
Silica Silica is the major impurity species in the BWR coolant, with concentrations typically 10 to 100 times greater than other impurities. The majority of industry evidence indicates that silica has a very small effect on IGSCC. Operating at Reactor water concentrations of 5 500 ppb eliminates lGSCC concerns. However, thermodynamic considerations suggest some concern for fuel cladding corrosion for high burn-up fuels.
A number of plants hcve operated with silica concentrations around 200 ppb and elevated feedwater metals at moderate fuel bum-ups without fuel failures. Also, Japanese BWRs have operated with silica concentrations 51 ppm with no reported fuel failures.
[5]
pH The pH of the liquid environment has been demonstrated to have an important influence on IGSCC initiation times for smooth stainless steel specimens in laboratory tests. However, although pH is routinely monitored in nuclear plants, accurate measurement is very difficult unless the conductivity is greater than 1 pS/cm. Because this Procedure generally requires lower conductivities, pH is not regarded as a useful watbr chemistry control parameter. Nevertheless, pH can serve as a useful diagnostic parameter for interpreting severe water chemistry transients and pH measurements are recommended for this Procedure.
4.3 CONDENSATE AND FEEDWATER SYSTEMS (From the condenser hotwell up through all feedwater heaters)
Proper system flushing for removal of corrosion products from the feed system prior to and during startup requires provision of a recirculation circuit from after last feedwater heater to hotwell. Circulation is provided by condensate pumps. Capacity equal to that from one condensate pump is adequate. The quality of feedwater should be brought to the same levels as required for plant operation at 510% power by recirculation with condensate pumps through Condensate Domineralizers with a return ta condenser hotwell after the feedwater heaters.
4.4 REACTOR SHUTDOWN - RESIDUAL HEAT REMOVAL (RHR) SYSTEM After' Torus Cooling Mode" Operation and prior to starting Shutdown Cooling, the RHR portion of the system should be flushed with water of the quality specified in the Condensate Storage Tank. Flushing should reduce corrosion product (metallic impurities) concentrations.
5.0 SPECIAL TOOLS AND EQUIPMENT None 7.8.1 Rev.13 Page 17 of 38
6.0 PRECAUTIONS AND LIMITATIONS
[1]
Technical Specifications Sections j
(a) 3.6.B.2 (b) 3.6.B.3 (c) 3.6.B.4 (d) 3.6.B.5 (e) 4.6.B.2 (f) 4.6.B.3
[2]
EPRI Water Chemistry Guidelines define key water chemistry control parameters to limit degradation of Reactor Coolant System components and materials. Less stringent Control Limits and actions are not permitted without the review and approval of the 4
Senior Vice President, Neclear. This restriction does not apply to Ach!svable Values, which may be waived by the Chemistry Department Manager.
l 7.0 PREREQUISITES i
None 4
3 i
1 l
7.8.1 Rev.16 Page 18 of 38 I
.---.m
8.0 PROCEDURE NOTE The following rationale was used for establishing water chemistry control parameters and developing recommendations relative to the need to take corrective action if a parameter exceeds a specified value:
Ingress of impurities into the Reactor Coolant System (RCS) should be kept to a practical and achievable rninimum.
Action levels should be based on quantitative information about the effects of.the chemistry variables on the corrosion behavior of RCS materials, fuel performance, and radiation field buildup. In the absence of quantitative data, prudent and achievable action level values should be specified.
Recommended control and diagnostic parameters should be reliably measurable at the levels specified using currently available equipment and Procedures The limits presented in this Procedure, with the exception of ECP, are the same for HWC and normal water chemistry. This is because the addition of hydrogen to the feedwater is not expected to adversely affect the concentrations of aggressive ions in the Reactor water that influence IGSCC of stainless steels. Without hydrogen injection, the limits presented in this Procedure will not prevent IGSCC of sensitized stainless steel components in BWRs, although they should minimize its rate of progression. HWC is capable of suppressing IGSCC during power operation and should be used whenever possible. HWC in no way allows for the relaxation of other water quality limits.
[1]
OBTAIN results from analysis (QB REVIEW data from instrument).
[2]
DETERMINE applicable section of this Procedure for parameter (s) in question.
UNDERSTAND that not all parameters / analyses are addressed herein.
SECTION SYSTEM (S) 8.1 Reactor Water (Reactor Coolant) (also see Attachment 7) 8.2 Reactor Feedwater/ Condensate 8.3 Control Rod Drive / Condensate Demineralizer Effluent 8.4 Miscellaneous Systems (e.g., RWCU, CST, TWT) 7.8.1 Rev.16 Page 19 of 38 l
J
l 8.0 PROCEDURE (Continued)
NOTES 1.
Refer to Section 3.0 as needed to clarify the definitions of, and responsibilities associated with, the acthns given in this Procedure. Be sure to understand the difference between Control Limits (e.g., Technical Specifications, EPRI Action Levels, GE Fuel Warranty) and Achievable Values.
2.
Less stringent Control Limits and actions are not permitted without the review and approval of the Senior Vice President, Nuclear. This restriction does not apply to Achievable Values, which may be waived by the Chemistry Department Manager.
[3]
PROMPTLY COMPARE results/ readings with corresponding limit (s) or value(s). E time permits, VERIFY that unexpected results are valid.
(a)
E any are above the Control Limit, Itigli the Chemistry Technician should PERFORM the following:
TAKE immediate corrective actions (if possible) to return parameter (s) to acceptable level (s).
NOTIFY Chemistry Supervision and then the Nuclear Watch Engineer of all limits which have been exceeded. INDICATE which, if any, Action Level has been reached (use Section 3.2).
INCREASE sampling / monitoring frequency stiQ CONTINUE TO TREND parameter (s) of concern. RECORD maximum (worst case) level (s) observed.
(b)
E any are above the Achievable Value,ItiEti, E POSSIBLE, NOTIFY Chemistry Supervision.
(c)
E results are below Control Limit and/or Achievable Value EMI trending toward exceedance, IlBiti USE your judgment to determine appropriate actions (for example, if Action Level will probably be reached before next results are obtained).
[4]
TAKE appropriate actions to identify and address the cause of any suspicious data or abnormal trends. DETERMINE whether a Problem Report should be submitted (required for Technical Specific 6 ions violations and upon entering Action Level 2 or 3).
E guidance is needed, DISCUSS with Chemistry Supervision and/or the NWE.
7.8.1 Rev.16 Page 20 of 38
-_____a
8.1 REACTOR WATER (see also Attachment 7)
[1]
Cold Shutdown (Nonpressurized)
PNPS EPRI EPRI GE Fuel Control Frequency of Tech Achievable Action Level Value Prior Warranty Parameter Measurement Seas yaha 1
2 3
To Startuo *" Continuous.
l Limit Conductivity
- Continuously N/A 51.5
> 2.0 51.0 2.0 (pS/cm)
(CH 1A)
Chloride Daily (a)
N/A 5 20
> 100 5100 100 (pob)
(CF-1 A)
Sulfsie Daily (a)
N/A
> 100 5100 N/A (pob)
(CF 1A)
I pH (CH 1A)
Daily (a)
N/A 5.3 to 8.6 Grab samples may be taken daily [(a)] If continuous measurement is not possible.
If Technical Specifications limits are exceeded, an orderly shutdown of the unit shall be inhiated and the Reador in Hot Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and Cold Shutdown within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
When a Continuous Limit is exceeded, reduce value to within Continuous Limit.
j (a)
Frequency should be daily unless plant conditions do not permit sampling by established Chemistry Procedures or by dip samples duilng outages.
(b)
Dissolved oxygen must be less than 300 ppb before Reactor water temperature is increased above 140*C (264*F).
(c)
Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if conductivity > 1.0 pS/cm.
7.8.1 Rev.16 Page 21 of 38 1
8.1 REACTOR WATER (Continued)
[2]
< 100,000 lb/hr Steam Rate (or Hot Standby)
EPRI GE Fuel PNPS EPRI Value Prior Warranty Control Frequency of Tech Achievable Action Level lo
"* Continuous Egtamg.tg Measurement jing.g Vafve 1
2 3
Operation Limit l
Conductivity
' Continuously 2.0" s 0.5
> 1.0 > 5.0 51.0 1.0 pS/cm CH 15 Chloride Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 100" 52
> 100 > 200 5 20 100 (p >b)
(CF 15)
Sulfate Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> N/A 55
> 100 > 200 5 20 N/A (p ab)
(Ch1A)
Total lodine Every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 20.0" s 0.1 N/A Cl/mi H-6B Dissolved
- Continuously N/A (b)
N/A (pa$)
Daily (a)
N/A 5.6 to 8.6 (c)
Total Zine Daily N/A 10 (8 to 12)
N/A (d)
(ppb)
Grab samples may be taken daily [(a)) If continuous measurement is not possible.
If Technical Specifications limits are exceeded, an orderly shutdowr of the unit shall be initlated and the Reador in Hot Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and Cold Shutdown within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
When a Continuous Limit is exceeded, reduce value to within Continuous Limit.
(a)
Frequency should be daily unless plant conditions do not permit sampling by established Chemistry Procedures or by dip samples during outages.
(b)
Dissolved oxygen must be less than 300 ppb before Reactor water temperature is increased above 140*C (284*F).
1 (c)
Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if conductivity > 1.0 pS/cm.
(d)
Max 15 ppb in accordance with GEK 97060. If 3-day average exceeds 15 ppb, reduce zine injection rate.
If 15 ppb exceeded for three consecutive days, discontinue zine injection until less than 15 ppb.
l l
l 7.8.1 Rev.16 Page 22 of 38
8,1 REACTOR WATER (Continued)
[3]
Startup(*)
EPRI PNPS EPRI Value Prior GE Fuel Control Frequency of Tech Achievable Action Level To Power Warranty Parameter Measurement Sp.tg y.sha 1
2 3
Ooeration
"* Continuous Limit Conductivity
' Continuously 10.0"
$0.5
> 1.0 > 5.0 51.0 1.0 pS/cm CH15 Chloride Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 100" 52
> 100 > 200 5 20 100 (p >b)
(CF 15)
Sulfste Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> N/A 55
> 100 > 200 5 20 N/A
(
)
Dissolved
' Continuously N/A (b)
N/A O
n (CF 1A)
Totallodine Every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 20,0"
$0.1 N/A (pCl/mi)
Daily N/A 5.6 to 8.6 (c)
Total Zinc Daily N/A 10 (8 to 12)
N/A (d)
(ppb)
(a)
Startup is the period during power ascension from when the mode switch was placed in
- Start & Hot Stby" until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the mode switch goes to *Run".
(b)
Dissolved oxygen must be less than 300 ppb before Reactor water temperature is increased above 140*C (284*F), and must be maintained below this level at higher temperatures.
(c)
Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if conductivity is > 1.0 pS/cm.
(d)
Max 15 ppb in accordance with GEK g7060. If 3-day average exceeds 15 ppb, reduce zine injection rate.
if 15 ppb exceeded for three consecutive days, discontinue zinc injection until less than 15 ppb.
Grab samples may be taken dally if continuous measurement is not possible.
If Technical Specifications limits are exceeded, an orderly shutdown of the unit shall be initiated and the -
Reactor in Hot Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and Cold Shutdown within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
When a Continuous Limit is exceeded, reduce value to within continuous Limit.
7.8.1 Rev.16 Page 23 of 38
3 8.1 REACTOR WATER (Continued)
[4]
Power Operation PNPS EPRI GE Fuel Control Frequency of Tech Achievable Action Level Warranty l
Parameter Measuroment Spag Value 1
2 3
"* Continuous Limit ECP
- Continuously N/A 5 300
> 230 (mV SHE)
Conductivity
'Coritinuously 10.0" 5 0.10
> 0.30 > 1.0 > 5.0 1.0 (pS/cm)
(CH 1A)
Chloride Dally 1000" 51.0
>5
>20
> 100 100 (ppb)
(CH-1A)
Sulfete Daily N/A 52.0
>5
>20
> 100 (ppb)
(CH 1A) pHrange Daily (a)
N/A (CH 1A) 5.6 to 8.0 Totallodine Every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 20.0" s0.1 (pCl/ml)
Silica (ppb)
Daily N/A 5150 (CH 1A)
Boron N/A (ppb BO )
3 (CH 1A)
Oxygen (ppb)
- Continuously N/A (CH-1A)
TotalZine Daily N/A 10 (8 to 12)
N/A (b)
(ppb)
(a)
Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if conductivity is > 1.0 pS/cm.
(b)
Max 15 ppb in accordance with GEK 97060. If 3-day average exceeds 15 ppb, reduce zinc injection rate.
If 15 ppb exceeded for three consecutive days, discontinue zinc injection until less than 15 ppb.
Daily grab sampling (or intermittent data collection of ECP readings) is permitted if continuous measurement is not possible.
If Technical Specifications are exceeded, an orderly shutdown of the unit shall be initiated and the Reactor in Hot Shutdovm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and Cold Shutdown within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
When a Continuous Limit is exceeded, reduce value to within Continuous Limit.
7.8.1 Rev.16 Page 24 of 38
8.2 REACTOR FEEDWATER/ CONDENSATE
[1]
Power level less than or equal to 10% and feedwater being pumped to vesseI**
PNPS EPRI EPRI Control Frequency of Tech Achievable Action Level Value Prior to Parameter Measurement Eggg yalgt i
2 3
> 10% Power Foodwater
' Continuously N/A
$ 0.10 (a)
> 0.15
< 0.065 Conductivity (a)
(pS/cm)
(CH-1C)
Feedwater Grab N/A 51 Suspended Corrosion Products --
(NTU)(CH 1C)
Hotwell
- Continuously N/A
< 0.15 (a)
> 10 Conductivity -
(pS/cm)
(CH 1C)
CDE(D) or
- Continuously N/A
> 200
< 200 (a)
Feedwater (a)
Dissolved Oxygen (ppb)
(CH 1C)
Enlal (a) After est&blishing condenser vacuum (b) Polished condensate Grab samples may be taken if continuous measurement is not possible.
Since there are no applicable Technical Specifications limits for feedwater, Reactor power level is used to correspond with EPRI plant conditions (" modes") given in Section 3.2.1.
7.8.1 Rev.16 Page 25 of 38 i
____J
8.2 REACTOR FEEDWATERMONDENSATE (Continued)
[2]
Power level > 10%"
PNPS EPRI GE Fuel Control Frequency of Tech Achievable Action Level Warranty Parameter Measurement SatG Y.thig i
2 3
- " Continuous Limit Foodwater
- Continuously N/A
~ 0.06
> 0.065 0.065 Conductivity (pS/cm)
(CH-1C)
Hotwell
- Continuously N/A
< 0.08
>0.10
> 10.0 Conductivity
- C)
Foodwater Weekly-integrated N/A 5 0.10
>0.50 Total icWi.if Feedwater Weekly-integrated N/A 52.0
>5.0 Total 4
( H.
.1)
- Continuously N/A 20 50
< 15 20 to 50 Dissolved
> 200 C)
Condensate
- Continuously N/A 20 50
< 15 20 to 50 Dissolved Oxy en
> 200 H-1C)
Feedwater Weekly-integrated N/A
<2 52 Total Zinc H 17.B.1)
Grab samples may be taken if continuous measurement is not possible.
Since there are no applicable Technical Specifications limits for feedwater, Reactor power level is used to correspond with EPRI plant conditions (" modes") given in Section 3.2.1.
"* When a Continuous Limit is exceeded, reduce value to within Continuous Limit.
[3]
Individual Condensate Domineralizer prior to service PNPS EPRI Control Frequency of Tech Achievable Action Level i
Parameter Measurement Sang yalgt 1
2 3
Individual Grab N/A 5 0.065
{
Cond Domin Conductivity (pS/cm) 1 7.8.1 Rev.is
(
Page 26 of 38 L
8.2 REACTOR FEEDWATER/ CONDENSATE (C:ntinued)
GE FUEL WARRANTY
- " Continuous Max.
Extreme Total Metallic im >urities -
Filtrate p us Solids (ppb)
- 15 30 60 Fe, Cu, Ni, Cr Total Cu (ppb) 0.5 2.0 4.0
" Total Zn (ppb) 3.0 Metallic Analyses - Filtrate Fe (ppb) 1.0 2.0 4.0 Metallic Analyses - Filterable Solids Fe (ppb) 10 20 40 Feedwater Conductivity (pS/cm) 0.065 0.1 0.2 Cond Demin Effluent (CH-1C)
Conductivity (pS/cm) 0.065 0.1 0.2 Oxygen (ppb)(CH-1C) 20 to 50 20 to 200 20 to 500 Zine attributable to zinc injection implementation may be disregarded when considering the 15 ppb fuelwarrantylimit.
Total zine is to be maintained in accordance with GEK 97060.
"* See fuel warranty for definitions of continuous, max, and extreme.
8.3 CONTROL ROD DRIVE (CRD)/ CONDENSATE DEMINERAllZER EFFLUENT (CDE)
[1]
Power level > 10%"
Tech Achievable Action iavel Sp_tg Value 1
2 3
Conductivity CH 1C N/A 5 0.10*
> 0.15 (pS/cm)
< 50*
> 200 (ppb)
In order to achieve these values,it is necessary to have the source of CRD water be the effluent of the Condensate Demineralizers.
" Since there are no applicable Technical Specifications limits for CRD/CDE, Reactor power level is used to correspond vCh EPRI plant conditions (" modes") given in Section 3.2.1.
7.8.1 Rev.16 Page 27 of 38
8.4 MISCELLANEOUS SYSTEMS l
l NOTE The water quality recommendations appearing hereunder should be suitable and achievable for most foreseeable circumstances. However, unusual circumstances may arise which could require relaxation of an Achievable Value or a set of Achievable Values. In these situations, t
the Chemistry Department Manager's approvalis required for relaxation of the Achievable Value(s).
[1]
REACTOR WATER CLEANUP (RWCU) EFFLUENT DURING POWER OPERATION Frequency of Achievable Measurement y.glyg Conductivity Daily 5 0.10 (pS/cm)(CH 1B)
Silica ppb)(CH 18)
Daily 5150 DR 2036]
[2]
TORUS (CH-3A)
Conductivity (pS/cm)
Monthly 55.0 Chloride (ppb)
Monthly 5 200 Sulfate (ppb)
Monthly 5200 pH Monthly 5.8 to 7.5 Silica (ppb SiO )
Monthly 5500 2
Total Organic Carbon (ppb)
Monthly 5500
[3]
FUEL POOL (CH-2F) (a)
Conductivity (pS/cm)
Weekly 51.0 Chloride (ppb)
Weekly 5100 Sulfate Weekly 5100 pH Weekly 5.8 to 7.5 Silica (ppb)
Weekly N/A (DR 2036)
TOC (ppb)
Weekly 5200 (a)
Frequency should be weskly unless piant conditions do not permit sampling by established Chemistry Procedures or by dip samples during outages.
7.8.1 Rev.16 Page 28 of 38
8.4 MISCELLANEOUS SYSTEMS (Continued) f Frequency of Achievable Measurement yghtg
[4]
CONDENSATE STORAGE TANKS (CH-2D)
Conductivity (pS/cm)
Weekly 51.0 Chloride (ppb)
Weekly 55 Sulfate (ppb)
Weekly 55 pH Weekly 5.8 to 7.5 Silica (ppb)
Weekly 5 20 Boron (ppb)
Weekly 5 50 Total Organic Carbon (ppb)
Weekly 5100
[5]
DEMINERALIZED WATER STORAGE TANK (CH-2E)
Conductivity (pS/cm)
Weekly 51.0 Chloride (ppb)
Weekly 55 Sulfate (pbb)
Weekly 55 pH Weekly 5.8 to 7.5 Silica (ppb)
Weekly 5 20 Boron (ppb)
Weekly 5 50 Total Organic Carbon (ppb)
Weekly 5100
[6]
- MAKEUP DEMINERAllZERS (Mixed Bed Effluent)(CH-32)
(* If these values are exceeded, then secure this system.)
Conductivity (pS/cm)
Continuously 5 0.07 "
Chloride (ppb)
Shiftly 55 Sulfate (ppb)
Shiftly 55 pH Shiftly 5.8 to 7.5 Silica (ppb)
Shiftly 5 20 Total Organic Carbon (ppb)
Shiftly 5 50 Via in-line measurement
[7]
CLOSED COOLING WATER SYSTEMS (CH-2B and 2C)
(RBCCW, TBOCW, and Station Heating Systems) pH Weekly 8.8 to 9.4 Nitrite (ppm NO )
Weekly
> 500 2
Chloride (ppm)
Weekly 57.5 Metals (NI, Cu, Fa, Cr)
Quarterly 5200 ppb
"* Metals analysis not required for Station Heating System.
7.8.1 Rev.16 Page 29 of 38
(
8.4 MISCELLANEOUS SYSTEMS (Continued) a Frequency of Achievable Measurement Malyg
[8]
TREATED WATER TANKS (CH-27)
Conductivity (pS/cm)
Each Batch 51.0 Chloride (ppb)
Each Batch 55 Sulfate (ppb)
Each Batch 55 Nitrites (ppb)
~ Each Batch 55 pH Each Batch -
5.8 to 7.5 SilicH, ppb)
Each Batch 5 20 l
Boron (ppb)
Each Batch 5 50 Total Organic Carbon (ppb)
Each Batch 5100 TOC (During Extended Outages)(ppb)
Each Batch 5200 Turbidity (NTU)
Each Batch 51.0 9.0 -
ACCEPTANCE CRITERIA None 10.0 ATTACHMENTS ATTACHMENT 1 - EPRI RECOMMENDATIONS FOR CONTINUOUS PROCESS INSTRUMENTATION (TABLE)
ATTACHMENT 2 - EPRI RECOMMENDED SAMPLING AND ANALYSIS FREQUENCY FOR CONTROL AND DIAGNOSTIC PARAMETERS DURING POWER OPERATION (TABLE)
ATTACHMENT 3 - CONDUCTIVITY / CONCENTRATION RELATION FOR VARIOUS CHEMICALS (TABLE)
ATTACHMENT 4 - VARIATION IN CONDUCTIVITY OF CHLORIDE AND SULFATE SOLUTIONS AT 25*C (GRAPH)
ATTACHMENT 5 - MAXIMUM POSSIBLE CHLORIDE CONCENTRATION FOR ANY GIVEN CONDUCTIVITY FOR COMMON CHLORIDE COMPOUNDS (GRAPH)
ATTACi' MENT 6 - RESTRICTIONS IMPOSED BY THE CONDUCTIVITY /pH RELATION (GRAPH)
ATTACHMENT 7 - REACTOR WATER QUALITY LIMITS FOR VARIOUS PLANT CONDITIONS ATTACHMENT 8 - lDENTIFYING CHEMISTRY EXCURSIONS (TABLE) 7.8.1 Rev.16 Page 30 of 38
ATTACHMENT 1 Sheet 1 of 1 EPRI RECOMMENCATIONS FOR CONTINUOUS PROCESS INSTRUMENTATION Cation Crack Hydvgen Radiaton Conductivity Conductivity Oxvoen Sodium ECP-Growth Flow Rate Level Reactor Water Control Control Control Confirmatory RWCU Outlet Diagnostic Diagnostic Feedwater Control Control Polished Diagnostic Condensate Diagnostic individual Condensate Polisher Outlets Diagnostic Individual Diagnostic
- Hotwells Diagnostic
- Diagnostic
- Contro! Rod Drive Cooling Water Control Diiigsustic Main Steam Line Either conductivity, cation conductivity, or sodium instrumentation can be applied.
7.8.1 Rev.16 Page 31 of 38
~.
EPRI RECONNENDED SAMPLING AND ANALYSIS FREQUENCY FOR l
ATTAct9ENT2 CONTROL AND DIAGNOSTIC PARAMETERS DURING POWER opt:MATION l
Sheet 1 of 1 -
Polished CRD instrument ReactorWater RWCU Outlet Feedwater Condensate Condensate ControlWater Venficabon Control Diaanostic Diannostic Control Dimanostm Control Dimanostic ConInd Conductmty(=)
Daily 7:x:#-
Daily Wealdy Daily atWeek Oxygen (b) 7 x:#
vi;d#.
vi;c#
Weeldy weeur l
ECP Weekly independent Parameter Measurement M8)
-(c)
Chloride Daily -
Sulfate Daily Sodium (9)
Weeldy Anions (d)
Weekly Silica Daily Daily iron Weekly Weekly (*)
Monthly 6)
Monthly 0)
Copper Weekiy Weeldy(*)
Montwye)
MonwyF)
Isotopics Weekly Weekly Monthly Monthly Hydrogen (h)
. (t) Laboratory estumentaton used for measurement of flowing sample forindependent.,xsm of irwine instruments.
(b) Cross-check of in-line instrumentabon with laboratory instrument or by grab sample techniques.
(c) Dady if Action Level 1 conduckwity is exceeded.
(d) Analyses for all strong acid anions (e.g., SO =, F, NCT. and 7) by ion chromatography is recommended.
4 3
( ) It is suggested that samples be removed from the integrahng sample colloclion device more frequeney (e.g.,3 times perweek) and anstyzed indmdually.
' (f) Frequency should be increased to weekly if Action Level i values for feedwater iron or copper are exceeded.
(g) The sodium concentrabon may be estmated from Na-24 measurements once a baseline is established for the ratio of sodium to Na-24 at each unit.
(h) As requred for calibru5on of platmum reference electrode.
7.8.1 Rev.16 Page 32 of 38
f ATTACHMENT 3 Sheet 1 of i CONDUCTIVITY / CONCENTRATION RELATION FOR VARIOUS CHEMICALS Concentration. Dob. at Indicated Conductivity at 25'C Species 0.2 uS/cm 0.3 uS/cm 0.5 uS/cm 1.0 uS/cm 5.0 uS/cm Sodium Sulfate 81 132 245 518 2670
- Sodium 26 43 80 168 850
- Sulfaie 55 89 165 350 1820 Sodium Chloride 67 114 206 438 2290
- Sodium 26 45 81 172 900
- Chloride 41 69 125 266 1390 Sodium Hydroxide 31 49 82 165 817
- Sodium 18 28 47 95 470 1
Cupric Hydroxide 38 58 98 196 972
- Copper 25 38 64 128.
635 Sulfuric Acid (a) 22 33 57 112 672
- Sulfate 21.5 32 56 110 560 Hydrochloric Acid (a) 16.5 25 43 85 428
- Chloride 16 24 42 83 416 Carbonic Acid (a) 65 127 317 1100 23800
- Carbon dioxide 46 90 225 780 16900 l
(a) Indicated conductivity equal to cation conductivity for the acid forms.
Note that the concentration of chloride required to obtain a given conductivity is two to four times less if the chloride is present as hydrochloric acid rather than as a chloride salt.
A similar relation holds for sulfate.
7.8.1 Rev.16 Page 33 of 38
ATTACHMENT 4 T
She:t 1 of 1 l
VARIATION IN CONDUCTIVITY OF CHLORIDE AND SULFATE SOLUTIONS AT 25'C s
10 i
i i
i i
i i
i 5.0 2.0 H SO4 2
g 1.0 1
~ 0,5 Nacl g
0.2 Na2SO4
~
z 8
0.1 0.05 0.02 0.01 1
2 5
1 20 50 100 200 500 1000 ANION CONCENTRATION (ppb) 07003%1 7.8.1 Rev.16 Page 34 of 38 m-
-u
ATTACHMENT 5 t
Sheet i cf 1 l
MAXIMUM POSSIBLE CHLORIDE CONCENTRATION FLiliiY GIVEN CONDUCTMTY FOR COMMON CHLORIDE COMPOUNDS 10 i
i i
i i
i
..i g
2 43 1.0 4
O k
E-
<C t-2 l-S 0.1 Oz-O O
I 0.01 1.0 10 100 1000 MAXIMUM POSSIBLE CHLORIDE CONCENTRATION (ppb) 070026A2 7.8.1 Rev.16 Page 35 of 38
I' ATTACHMENT 6 i'
Sheet 1 of 1 RESTRICTIONS IMPOSED BY THE CONDUCTIVITY /oH RELATION 100 g
i i
y g
~
POSSIBLE REGION 10 hcl NaOH x
1.0
/
0.1 IMPOSSI LE REGl0N
/IMPO IBLE RE lON j
0.01 Ii
/I I
I I
I/
4 5
6 7
8 9
10 11 pH otoo2 43 7.8.1 Rev.16 Page 36 of 38
I-REACTOR WATER QUALITY LIMITS FOR ATTACHMENT 7 f
VARIOUS PLANT CONDITIONS i
Sheet 1 of 1 Different control limits are in effect for various p! ant conditions, depending upon mode switch positioni coolant temperature, power level (steaming rate), elapsed time in a given status, etc.
The following four terms have been adapted from varit.us sources - see Definitions (base document Section 3.0) for clarification.
[1]*
Cold Shutdown - Reactor coolant temperature less than or equal to 212*F, Reactor vessel nonpressurized (no steam being generated). Also, termed " cold condition".
[2)*
Except during startup, _< 100K refers to either.
(a)
< 100,000 lb/hr - When the unit's steaming rate is less than 100,000 pounCs/ hour (Reactor < 1% design power level) and coolant temperature > 212*F.
9B (b)-
Hot Standby - Mode switch in " Start & Hot Stby"",d. coolant temperature > 212*F, Reactor pressure < 600 psi, and the MSIVs close
[3)*
Startup - The period during power ascension from when the mode switch was placed in
" Start & Hot Stby"" until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the mode switch goes to "Run".
[4)*
Power Operation - Mode switch in "Run" (or " Start & Hot Stby""), Reactor power above 1% (steaming rate > 100,000 lb/ hour), and more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since startup commenced.
Verify proper limits and associated action (s) by refsrring to base document S' actions 8.0 and 8.1 of this Procedure.
Reactor Water (Primary Coolant)
- Definition #................................ [1' L2)
[3]-
[4]
Plant Condition...........................Co d
< 100K S/U Pwr Ops PARAMETER LIMITNA.UE
- Conductivity Achievab e Value
< 1.5
< 0.5
<0.5
<0.10
[ S/cm)
Action Level 1 52.0 1/A
~N/A-5 0.30 Action Level 2 N/A-
> 1.0
> 1.0
> 1.0 Action Level 3 N/A
> 5.0 -
>5.0
> 5.0 Tech Spec N/A 2.0 10.0 10.0 Chloride Achievable Value
<20
< 2.0 e 2.0
< 1.0 -
[ ppb)
Action Level 1 5100 N/A N/A 55.0
~
~
Action Level 2 N/A
' > 100
> 100
> 20 Action Level 3 -
N/A
> 200
> 200
> 100 Tech Spec N/A 100 100 1000.
Sulfste-Achievable Value N/A-
< 5.0
< 5.0
< 2.0 --
- [ ppb)
Action Level 1
> 100 N/A 1/A 55.0
~
Action Level 2 N/A
> 50
> 100
> 20 Action Level 3 N/A
> 100
> 200
> 100 Tech Spec (there are no Tech Spec limits for sulfate) 7.8.1 Rev.16 i Page 37 of 38 3
ATTACHMENT 8 ^
Sheet 1 of 1 IDENTIFYING CHEMISTRY EXCURSIONS EXCURSION PRINCIPAL ID SECONDARY ID SYMPTOM SYMPTOM Resin injection Reactor Water Reactor Water increased Main Steam Line Reactor Water Conductivity increase Sulfate (SO )and Radiation Monitor pH Decrease 4
Nitrate (NO )
Concentrations High Condenser Hotwell Conductivity Hotwell Chloride CDE Conductivity Reactor Water in-Leakage increase Concentration increase Conductivity and increase Chloride increase Trichloroethane -
Reactor Water Reactor Water Reactor Water Main Steam Line (Cl -CH-CH -Cl)
Chloride Concentration Conductivity pH Decrease Radiation Monitor 2
2 Transient increase tHCl)
Increase Ethylene Glycol Hotwell Conductivity Offgas Flow Decrease Minor Reactor Fuel Pool HO-CH -CH -OH Transients Before Recombiner, Water Conductivity Conductivity 2
2 Recombiner Temperature increase and pH Increase After Decrease, Main Steam Decrease.
Makeup Line Radiation Montior No Chloride Change Transient Lube Oil Feedwater Turbidity Main Steam Line Increase in Hotwell Conductivity increase.
Increase Radiation Monitor Condensate Demin Minor Reactor Water Transient, Offgas Resin delta P Conductivity increase
(
Hydmgen Concentration increase Urea (Turco, Reactor Water increase in Reactor No Change in Reactor Decon)
Conductivity increase Water Nitrate (NO )
Water Chloride 3
Concentration H NCO NH2 2
Exhausted Anion Conductivity increase pH Decrease Chloride Increase Sulfate increase l
Resin 7.8.1 Rev.16 Page 38 of 38
4 J
e' l
ENCLOSURE 2 GENE Letter No. HSM-9721, "The Use of DLL Computer Program in Pilgrim Nuclear Station Core Spray Analysis", dated July 29,1997 l
GE NuclearEnergy Engineering & Ltcensing Consulting Services 175 Curtner Avenue, MC 747 San Jose. CA 95125 Phone / Fax:(108) 925-5029/1150 f-IISM-9721 July 29,1997 Mr. J.S. Roberts Boston Edison company 800 Boylston Street Boston, MA 02199
Subject:
The Use of DLL Computer Program in Pilgrim Nuclear Station Core il pray Analysis
References:
(1) " Evaluation of Indications Detected in the Annulus Core Spray Piping at Pilgrim Nuclear Station," GE Report No. GE-NE-B13-01869 028, Rev. O, March 1997.
(2) NRC Evaluation of BWRVIP-01 (Core Shroud Inspection and Flaw Evaluation Guideline).
(3) "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines," BWRVIP-18.
Dear Steve,
This letter is intended to provide technical justification for the use of DLL (Distributed Ligament Length) computer program in the Reference 1 Analysis.
The DLL computer program was used in Reference 1 to evaluate indications detected at the collar to shroud welds. This computer program was developed by GE as a part of work on BWRVIP-01 (Reference 2).
BWRVIP-01 describes -the formulation and methodology of the DLL computer program. The methodology is essentially based on the limit load methods of Appendix C of ASME Section XI. The approtch used in DLL is useful when there are more than one uncracked ligaments at a circumferential weld to be evaluated. The NRC review in Reference 2 accepted this methodology (See Attachment A) in connection with the evaluation of shroud cracking. Since both the shroud and the core spray piping are cylindrical structures, the same methodology is applicable to core spray piping also.
Reference 3, currently under review by the NRC, states that the rqethodology of Reference 2 can be used to evaluate the core spray indications. In the interim, GE believes
,, J ?
that given the NRC's acceptance of DLL methodology for core shroud applications, the same methodology can be used on a case basis.
The analysis in Reference 1 even considered a scenario in which no credit was taken for the moment carrying capability at the collar welds where the indications were evaluated using the DLL program. This analysis showed that even with this extreme assumption, the ASME Code and flow-induced vibration (FIV) criteria are satisfied. GE has conducted similar analyses for one US BWR plant (Vermont Yankee) which was accepted by the NRC as technicsjusti6 cation for continued operation.
To summarize, GE believes there is sound technical justi6 cation for the use of DLL computer program in the analysis of Reference 1.
Please call me if you have any further questions.
- Regards, H.S. Mehta Principal Engineer, Engineering & Licensing Consulting Services cc:
M. Shepherd e
l ENCLOSURE 3 NRC Letter B.W. Sheron Director Engineering NRR to J.T. Beckham Chairman BWRVIP,
- Evaluation of BWR Shroud Cracking Generic Safety Assessment, Revision 1, ' GENE 523-
. A107P-0794, August 5,1994 and 'BWR Core ShroudInspection and Evaluation Guidelines',
GENE-523-113-0894, September 2,1994", dated December 28,1994.
[ Note: This is Attachment A (Reference 2) discussed in GENE Letter, HSM-9721, dated July 29,1997)
_ _ _. _