ML20212H252
| ML20212H252 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/02/1987 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-87025, NUDOCS 8703060053 | |
| Download: ML20212H252 (8) | |
Text
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.jA PENHI NYN-87025 gggg New Hampshire Yankee Division March 2, 1987 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
References:
(a) Facility Operating License No. NPF-56 Docket No. 50-443 (b) PSNH Letter (SBN-1211) dated October 9,-1986, "10 CFR 50.59 Evaluations" G. S. Thomas to V. S. Noonan
Subject:
10 CFR 50.59 Quarterly Report Gentlemen:
Enclosed please find the Quarterly Report of 10 CFR 50.59 Safety Evaluations for Seabrook Station. This report covers the period of October 17,1986, (date of issuance of Low Power License) to December 31, 1986, and is being submitted pursuant to the reporting requirements outlined in Reference (b).
Should you require further information regarding this matter, please contact Mr. Warren J. Hall at (603) 474-9574, extension 4046.
Very truly yours, d
l George S. Thomas l
Enclosure cc: Regional Administrator USNRC Region I.
631 Park Avenue King of Prussia, PA 19406 l-Mr. A. C. Cerne NRC Senior Resident Inspector Seabrook ctation Seabrook, NH 03874 o
P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574
ENCLOSURE TO NYN-87025'.
SEABROOK STATION 10 CFR 50.59~ SAFETY EVALUATIONS
-QUARTERLY REPORT'.
! OCTOBER 17, 1986 T0 DECEMBER 31, 1986 j1. ^ Design Changes
' The below listed design changes have b'een 'made at_ Seabrook Station and
- evaluations have been performed pursuant'to the requirements of 10-CFR 50.59.
E Design Change Request: Number 425
Title:
. Meteorological Tower Power Supply
==
Description:==
This design change request has been incorporated to provide a back up power supply to Seabrook Station's Meteorological Tower. LThe need for the backup power source for the:
Meteorological Tower was documented as an open item during the NRC's Emergency-Plan T.mplementation Appraisal, Inspection Report 50-443/85-32.
This design' change provides' normal power to-the
. meteorological tower from the off-site power source and backup power from the _ Unit 1 ~ A Diesel Generator during loss :
of off-site power.. This design change ensures the availability of meteorological data during loss of off-site power. The Meteorological System is classified as nonsafety.
related.~
This design change adds esbles and replaces the circuit breaker _in MCC-E523 with a larger breaker.. The cables being used are qualified cables.and the new circuit breaker meets the same-design requirements as similiar breakers in MCC-E523.- The addition of the meteorological tower load to the A Diesel Generator has been evaluated and is within the allowable limits of FSAR and Regulatory Guide 1.9.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design. change and it has been determined that'this change g
will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Change Request: Number 480
Title:
Sump Header Reroute to Chemical Drain Treatment Tank
==
Description:==
The implementation of Design Change Request Number 480 was necessary to eliminate a possible source of chemical and oil contamination from entering the Waste Liquid Drain System.
The design change re-routed three sump pump discharges, Pump 77B, Pump 77C, and Pump 230, from the Floor Drain Tanks to the Chemical Drain Treatment Tanks for processing. A 1
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TENCLOSURE:TO'NYN-87025
- potpourri of chemicals (nitrates, chlorides, : sulfates,. heavy 7
metals, soap, detergents, hydrocarbons, acids and caustics) could cause corrosion and. corrosion cracking of inconel or~
stainle'ss steel.and is a highly undesirable discharge into the Floor Drain Tank.
The.re-routing of WLD-2092-2-2" to implement this; design change was reviewed for any possible safety implications.
The system design change was implemented to ANSI B31.1 i-requirements. -Evaluations were performed toLidentify any environmental impact and conformance-to Seabrook Station NPDES permit.. Operation evaluations, ALARA evaluations, Equipment Qualification evaluations, and Human Factors evaluations were also performed for any possible adverse consequences.
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==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not~ create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will'be incorporated by means of a future amendment.
' Design Change Request: Number 557
Title:
Nitrogen Supply to Containment Electrical Penetrations
Description:
Design Change Request Number 557 was originated to provide a
. permanent nitrogen supply system to each electrical penetration seal in order to maintain a 15 psig pressure on the o-ring seals to maintain environmental qualifications.
Before this design change was undertaken, New Hampshire Yankee requested Westinghouse Electric Corporation to review the monitoring volume pressure requirements in the Westinghouse supplied electrical penetration assemblies.
Westinghouse Electric Corporation responded to this request with a review of their requirements to maintain a continuous monitored pressure on their electrical penetrations. The results of this review have indicated that the electrical penetrations will perform their intended design function with their monitoring volume unpressurized.
New Hampshire Yankee Engineering has reviewed the results of this report and has found it to be acceptable.
Conformance to the requirements of 10 CFR 50 Appendi.t J, E
Part II to pass a Type "B" test will be maintained on a schedule consistent with the requirements of Seabrook-Stations Technical Specifications and 10 CFR 50 Appendix J, Part III.D. 2.
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t ENCLOSURE TO NYN-87025 A 10 CFR'50.59 safety evaluation was-performed for this
==
Conclusion:==
-change in response to a commitment-to IE Bulletin 77-07 as-
. stated'in, SB-5743, dated January 23,-.1978.
The use of unpressurized-containment electrical penetrations will not
- create an unreviewed safety concern.. Changes to the Final Safety' Analysis. Report will be incorporated by means'of a future amendment.
Design Change Request: Number 675
Title:
Change in Environmental Requirements for Components in Environmental Zone PB-11
Description:
. Design "hange Request Number 675 was developed to incorporate a change in the environmental. requirements-for components in Environmental Zone PB-11, PCCW Pump Area, Elevation 25'-0",
located in.the Primary Auxiliary Building. Revised calculations have been developed for PB-11:that shows the maximum temperature, as a result of a Loss of Coolant Accident (LOCA), is 130*F.
The previous analysis had listed the maximum temperature in this area as 135'F.
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The only. type of-accident that could cause a temperature of 135*F would be.a High Energy Line Break (HELB) and the components within PB-11 were reviewed to verify'that their-operability would not be required during this type of accident. For components required to function during a
.LOCA,' Main Steam Line. Break (MSLB) and/or a Fuel-Handling-Accident (FRA), the environment can be declared mild.
Seabrook Stations project criteria for a mild environment are temperature j( 130*F, : pressure j( 1.0 EgIG, humidity <
100% condensing, and radiation < 1.0 x 10 rads.
This design. change will result in Seabrook Station revising the Class IE Equipment'and Harsh Environment Equipment List. The revised list will alleviate the necessity of overclassification of the components in PB-11 in regards to maintenance requirements and replacement costs.
==
Conclusion:==
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined t hat - this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
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- D ENCLOSURE TO NYN-87025
.2.
Temporary Modifications Tne-below listed - temporary modification has been made at Seabrook Station and an evaluation has been performed pursuant to the requirements of 10 CFR 50.59.
Temporary Modification Request: Number 86-123
Title:
Addition of N Cover Gas to Boric Acid Tank "A" 2
==
Description:==
Temporary modification 86-123 has been incorporated at Seabrook Station to eliminate a problem with maintaining.the
~ dissolved oxygen concentration in the Reactor Coolant System-within Technical Specification Limits. The temporary.
modification consists of adding a nitrogen cover gas to Boric Acid Tank-4A to guard against the addition of oxygen to the Reactor Caolant System. This modification is only temporary because of-the valve line-ups required by the restrictions in Seabrook Station Low Power License to maintain the > 2000 PPM boron concentration level in.the Reactor Coolant System.- The modification will be removed prior to Seabrook Station. entering Mode 2.
A safety evaluation has been performed to justify the addition of the nitrogen cover gas. Although the Boric Acid Tanks are designed to be atmospheric storage tanks, an engineering safety evaluation of the tank vendor's calculations in conjunction with the applicable rules and criteria of the ASME Boiler and Pressure Vessel Code indicates that the tanks should be capable of withstanding an internal pressure of 3 inches (water) positive pressure to 3 inches (water) negative pressure over the normal range of tank level. The temporary modification has been designed so as not to violate the *3 inch water pressure limits.
==
Conclusion:==
A 10 CFR 50.59 Safety. Evaluation was performed for this temporary modification and it has been determined that the change will not create any unreviewed safety concerns.
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ENCLOSURE TO NYN-87025 3.
Technical Requirements Manual The below listed changes have been made to the Seabrook' Station Technical Requirements Manual and evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
Technical Requirements Manual Change Request: Number 86-001
-Title: Technical Requirement 14 - Table 16.3-9
==
Description:==
A change to Seabrook Station's Technical Requirement Number 14 has been made to revise Table 16.3-9 " Motor Operated Valves with Thermal Overload Protection Devices Operable at all Times".
The change in Table 16.3-9 incorporates new Overload Heater Catalog Numbers and their Heater Current Range (Amperes) values for feedwater motor-operated valves FW-V346 and-FW-V347. This change was necessitated because of an engineering design change that had been performed prior to the issuance of the Seabrook Station Low Power License.
A safety evaluation had been performed on the engineering design change to justify the change in the overload heaters for the motor-operated valves.
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performed for the change to the Technical Requirements Manual and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Technical Requirements Manual Change Request: Number 86-002
Title:
Technical Requirements - 13 and 15 - Tables 16.3-8 and 16.3-10 Respectively
==
Description:==
This change to the Technical Requirements Manual incorporates corrections of typographical errors in TABLE 16.3-8 Containment Penetration Conductor Overcurrent Protection Devices" and TABLE 16.3-10 " Protection Devices for Non-Class IE Circuits Connected to Class IE Power Sources". The change to TABLE 16.3-8 changes the test setpoint for MCC-E615, Thermal Barrier PCCW Recirculating Pump CC-P-332B(s) from 367-689 amps to 369-689 amps. The change to TABLE 16.3-10 changes the system powered by MCC-E514, 120Vac distribution panel, Circuit 3 from system powered ED to system powered SEC.
A safety evaluation has been performed to verify that the typographical error changes have been properly corrected to make the Tables consistent with other applicable documents at Seabrook Station.
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ENCLOSURE TO. NYN-87025 r
==
Conclusion:==
A 10 CFR 50.59 Safety Evaluation was performedLfor the change to the Technical Requirements Manual and it has been
-determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Technical Requirements' Manual Change Request: Number 86-003
Title:
Technical Requirements 13-Table.16.3-8
==
Description:==
A change to Technical Requirements Manual Table 16.3 " Containment Penetration Conductor Overcurrent Protection Devices" has been completed to correct a typographical error. On page.16.1-69 of Table 16.3-8, the heading for Test Setpoint (amps) column was given as "200%" and "200%"
and should have said "200%" and "300%" to correspond with the two different Test Setpoint settings.
A Safaty Evaluation has been performed to verify that the typographical error change will in no way affect the intent of Table 16.3-8
==
Conclusion:==
A 10.CFR 50.59 Safety Evaluation was performed for the change to the Technical Requirements Manual.and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis P.eport will be incorporated by means of a future ' amendment.
4.
Final Safety Analysis Report At the time of the issuance of the Low Power License, October. 17, 1986, Seabrook Station's Final Safety Analysis Report was in the process of revision. Many of the changes made to the Final Safety Analysis Report (FSAR) had previously been submitted to the NRC as commitments in various correspondence. ' Those changes which were incorporated into the last FSAR revision and not previously identified to the NRC are administrative changes and do not reflect design changes to Seabrock Station.
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4 ENCLOSURE.TO NYN-87025 5.
Procedure Changes-Procedure changes' that require review and approval by the Station Operation Review Committee (SORC) have been subjected to the requirements-of 10 CTR 50.59. No procedure changes have been made at Station during this reporting period that would require a change to^the Final _ Safety Analysis Report.-
6.
Test or Experiments There were no tests or experiments performed during this reporting period-that require evaluations in accordance with 10 CFR 50.59.
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