ML20083Q130
| ML20083Q130 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 05/19/1995 |
| From: | Gamberoni M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20083Q132 | List: |
| References | |
| NUDOCS 9505250124 | |
| Download: ML20083Q130 (8) | |
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UNITED STATES y
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'j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 300eH001 CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.165 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated December 29, 1994, as supplemented February 2 and May 4, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9505250124 950519 PDR ADOCK 05000255 P
, Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 165, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance with full l
implementation no later than startup from the 1995 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION I
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Marsha Gamberoni, Project Manager Project Directorate III-l Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 19, 1995 i
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'd ATTACHMENT TO LICENSE AMENDMENT NO.165 FACILITY OPERATING LICENSE N0. DPR-20 DOCKET NO. 50-255 1
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
BEMOVE INSERT 3-79 3-79 3-79a 3-79b 4-13 4-13 4-15a f
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.i' 3.18 Deleted v
3.19 IDDINE REMOVAL SYSTEM Snecification
.The Trisodium Phosphate (TSP) baskets shall be OPERABLE, containing.
2 8,300 pounds and s 11,000 pounds of active TSP.
Anolicability Specification 3.19 is applicable when the PCS is 2 300*F.
Action 3.19.1 With TSP not within limits, restore TSP to within limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.19.2 If the action required by 3.19.1 is not met and the associated completion time has expired:
a)
The reactor shall be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and b)
The reactor shall be placed in a condition where the affected equipment is not required, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
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Amendment No. 60, 44, 40, 43, 68, 440, 158, 462,
165 3-79 i
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3.19 IODINE REMOVAL SYSTEM 3.19 Basis Iodine Removal System Trisodium Phosphate (TSP) Baskets TSP is placed in baskets on the floor at 590 ft. elevation in the containment building to ensure that iodine, which may be dissolved in the recirculated reactor cooling water following a loss of coolant accident (LOCA), remains in solution and that a neutral pH is maintained. Recirculation of the water for core cooling and containment spray provides mixing to achieve a uni. form neutral solution pH. TSP also helps inhibit stress corrosion cracking (SCC) of austenitic stainless steel components in containment during the recirculation phase following an accident.
Fuel that is damaged during a LOCA will release iodine in several chemical forms to the reactor coolant and to the containment atmosphere. A portion of the iodine in the containment atmosphere is washed to the sump by containment sprays.
The SIRWT water is borated for reactivity control. This borated water, if left untreated, would cause the sump solution to be acidic.
In a low pH (acidic) solution, dissolved iodine will be converted to a volatile form. The volatile iodine will evolve out of solution into the containment atmosphere, significantly increasing the levels of airborne iodine. The increased levels of airborne iodine in containment contribute to the radiological releases and increase the consequences from the accident due to containment atmosphere leakage.
After a LOCA, the components of the safety injection and containment spray systems will be exposed to high temperature borated water.
Prolonged exposure to hot untreated sump water combined with stresses imposed on the components can cause SCC. The rate of SCC is a function of stress, oxygen and chloride concentrations, pH, temperature, and alloy composition of the components. High temperatures and low pH, which would be present after a LOCA, tend to promote SCC. This can lead to the failure of necessary safety systems or components.
Adjusting the pH of the recirculation solution to levels above 7.0 prevents a significant fraction of the dissolved iodine from converting to a volatile form. The higher pH thus decreases the level of airborne iodine in containment and reduces the radiological consequences from containment atmosphere leakage following a LOCA. Maintaining the solution pH above 7.0 also reduces the occurrence of SCC of austenitic stainless steel components in containment. Reducing SCC reduces the probability of failure of components.
The hydrated form of TSP cor.tains molecules of water attached to each molecule of TSP. That form of TSP is used because of the high humidity which might occ Ar in the containment building during normal operation. Since the TSP is hydrated, it is less likely to absorb large additional amounts of water than anhydrous (without water) TSP and will undergo less physical and chemical change.
Amendment No.165 3-79a
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'3.19 10 DINE REMDVAL SYSTEM s
AA111 Iodine Removal System TSP. Baskets (continued) j p
The quantity of TSP placed in containment is designed to adjust the pH of the sump water to be between 7.0 and 8.0.-
The pH needs to remain < 8.0 to remain within the assumptions of the analysis for post-LOCA Hydrogen concentration in the containment. That analysis concludes that hydrogen generation will not exceed the limits of Regulatory Guide 1.7.
Weicht limits: The minimum acceptable amount:of TSP is that weight which-will ensure a sump solution pH 2 7.0 after a LOCA, with the maximum amount'of water at the minimum initial pH possible in the containment sump; a maximum '
acceptable amount of TSP is that weight which could cause a sump solution pH of s 8.0 with a minimum amount of water at a maximum initial'pH.
The TSP is stored in wire mesh baskets placed inside the containment at the 590 ft. elevation. Any quantity between 8,300 and 11,000 lb. of TSP will result in a pH in the desired range.
i 33111 Applicability 3.19 TSP baskets support operation of the Safety Injection System, The Containment Spray System, and the SIRWT. Therefore, the TSP baskets are required to be OPERABLE when the PCS is greater than 300*F.
Raili Action Statements 3.19 The listed Action is required to be completed within the specified time if the conditions of the specification are not met. :If, prior to expiration of the specified completion time, the required conditions are restored,-
E completion of the Action is not required.
Each specified completion time-starts at the time it is discovered that the Action statement is applicable.
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Action 3.19.1 - TSP not within limit - If it is discovered that the TSP'in the containment building is not within limits, action must be taken to- '
restore the TSP to within limits. The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for restoring the TSP within limits, where possible, because 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is'the same time allowed for restoration of other ECCS components.
Action 3.19.2 - Reauired action AND associated completion time not' met - If the required action cannot be met within the associated completion time, the plant must be placed in a condition where the inoperable equipment is not required.
Twelve hours are allowed to bring the plant to HOT SHUTDOWN, and 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to. reach conditions where the affected equipment is not required, to avoid unusual plant transients. Both the 12 and the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> time periods start when it is discovered that Action 3.19.2 is' applicable.
l Amendment No.165 3-79b i
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3s 4.2:
EQUIPMENT SAMPLING AND. TESTS L
Table 4.2.2 (continued)
' Minimum Frecuencies for Eauinment Tests 12.
Iodine Removal System Verify the. Iodine. Removal System TSP baskets are OPERABLE by the following surveillance:
f a.
Verify the TSP baskets contain between 8,300 and 11,000 pounds of TSP each 18 months.
b.
Verify that a sample from the TSP baskets provides adequate pH adjustment of borated water each 18 months t
13.
Containment Purge and Ventilation Isolation Valves j
The Containment Purge and Ventilation Isolation Valves shall be determined closed:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by checking the valve position indicator in the control room.
b.
At least once every 6 months by performing a leak rate test between the valves.
- 14. Shutdown Cooling f
To meet the shutdown cooling requirements of Section 3.1.g:
a.
The required reactor coolant pump (s), $f not in operation should be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
b.
The required steam generator (s) shall be determined OPERABLE by verifying the secondary water level to be it-84% at least' once per'
)
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l c.
At least one coolant loop or train shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 15. Main Feedwater Isolation i
a.
Verify that the Main Feedwater Regulating valve and the associated bypass valve close on an actual or simulated Containment High' Pressure (CHP) signal once each 18 months.
1 b.
. Verify that the Main Feedwater Regulating valve and the associated bypass valve close on an actual or simulated Steam Generator Low.
Pressure (SGLP) signal once each 18 months.
I Amendment No. 81, 90, H8, 4H, He,165 4-13
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- Basis.- Table 4.2.2 Item 12 Trisodium Phosohate fTSP) Tests Item 12a, TSP quantity verification
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Verification of the quantity of. TSP.in the baskets ensures that neither
' leakage nor other water sources in the containment reduce the basket content below the required minimum. This requirement ensures that there is an r
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' adequate quantity of TSP to adjust the pH of the post LOCA sump ^ solution to a value between 7.0 and 8.0.
Item 12.b - TSP quality verification Periodic testing is performed to ensure the solubility and buffering ability of the TSP after exposure to the containment environment. Satisfactory completion of this test Tssures that the TSP in the baskets is " active" as required by Specification 3.19.
Adequate solubility is verified by submerging a representative sample of. TSP from one of the baskets in containment in un-agitated borated water heated to a temperature representing post-LOCA conditions; the TSP must completely dissolve within a~4 hour period. The test time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is specified to allow time for the dissolved TSP to naturally diffuse through the un-agitated-test solution. Agitation of the test solution during the solubility
- verification is prohibited, since an adequate standard for the agitation.
intensity (other than no agitation) cannot be specified. The flow and turbulence in the containment sump during recirculation would.significantly-decrease the time required for the TSP to dissolve.
1 Adequate buffering capability is verified by a measured pH of the sample solution, following the solubility verification, between 7 and 8.
The sample
- t is cooled and thoroughly mixed prior to measuring pH.
The quantity of the TSP sample, and quantity and boron concentration of the I
water are chosen to be representative of post-LOCA conditions.
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Amendment No.165 l
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