ML20237H302
| ML20237H302 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/28/1987 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NYN-87101, NUDOCS 8709030202 | |
| Download: ML20237H302 (10) | |
Text
- _______
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George S. Thomas
/
Vice President Nuclear Produchon i
6 Service of New HampeNro NYN-87101 1
Ntw Hampshire Yankee Division August 28, 1987 1
United States Nuclear Regulatory Commission Washington, DC 20555' l
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 l
April 1, 1987, to June 30,.1987, 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,
/
eorg S. Thomas Enclosure cc:
Regional Administrator USNRC Region I 631 Park Avenue
)
King of Prussia, PA 19406
{
Mr. A. C. Cerne NRC Senior Resident Inspector Seabrook Station Seabrook, NH 03874 8709030202 870828 PDR. ADOCK 05000443.
P PDR
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l P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574 1
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4 August 28,.1987 d
NYN-87101
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10 CFR 50.59 QUARTERLY REPORT Daley, W. J.
01-62 DeLoach, R. J. (3)
YAEC Harrison, R. J.
PSNH Sweeney, R. E. (3)
Bethesda Temple, W. J.
49-SS Ropes & Gray (3)
Boston Executive Offices 01-40 RSD/NSG Routing Copy 01-48 Subject File 01-48 File 0001 01-48 DCC 49-DC i
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l ENCLOSURE TO NYN-87101 SEABROOK STATION 10 CFR 50 59 SAFETY EVALUATIONS QUARTERLY REPORT APRIL 1, 1987 TO JUNE 30, 1987 1.
Design Changes The below listed design changes have been made at Seabrook Station and safety evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
Design Coordination Report Number 86-266
Title:
Chemical Drain Treatment Chemical Adjustments
==
Description:==
This Design Coordination Report was initiated to add connections to the Waste Liquid Drain System to allow chemical treatment and sampling of the Chemical Drain Treatment Tanks. The addition of the new piping connections will provide frr greater flexibility in system operations.
The Waste Liquid Drain System is not safety related.
==
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 futuro amendment.
Design Coordination Report: Number 86-673
Title:
Chemical Waste Stream Segregation
==
Description:==
p.esign Coordination Report Number 86-673 was implemented to eliminate a possible source of trace chemicals from the l
Chemical Drain Treatment Tank being discharged into the l
Floor Drain Tanks and ultimately into the Waste Liquid
)
Evaporators. The trace chemicals contain: (1) heavy metals that could plate out on the heat transfer surfaces in the evaporators and reduce evaporator efficiency; and (2) caustics / acids that could concentrate at the bottom of the evaporators and are detrimental to the stainless steel components in the evaporators. -
I
' ENCLOSURE TO NYN-87101 The design change provides an additional chemical stream flow path to segregate the Chemical Drain Treatment Tank and the Floor Drain Tanks by rerouting the chemical stream around the Floor Drain Tanks.
The rerouted chemical stream was tied into the discharge of the Floor Draias Purps, WL-P-91A & B.
Normally, the stream will be filtered through the Floor Drain Filters and collected in the Waste Test Tanks for final sampling and discharge.. If required, the original flow path to the Waste Liquid Evaporators is still available for treatment of the chemical stream from the Chemical Drain Treatment Tank.
This equipment is not safety related and the treatment of liquid radwaste will be sampled and monitored as described in the Final Safety Analysis Report and Technical Specifications.
==
Conclusion:==
A 10 CFR 50.5) 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 Coordination Report: Number 86-o76
Title:
Replacement of RWST Temperature SUitch
==
Description:==
This Design Coordination Report was initiated to replace the existing Reactor Water Storage Tank (RWST) high/ low alarm temperature switch with an improved switch.
The existing' temperature switch has a liquid filled; bulb and capillary sensor'which is inherently sensitive to ambient temperature variations. Thr new temperature switch has a vapor filled bulb and capillary sensor that will provid; a higher degree of accursay over a'large ambient temperature range; The new temperature switch does;not provide lor,a1 tmnperature indication. However, this information is currently available from an adjacent temperature, controller.
i The high/ low temperature switch is Non-clasa IE, but is mounted in accordance with seismic category I criteria.
l
==
Conclusion:==
.~A 10 CFR 50.59 saf ety evaluation yac Torforned.for,this I
'f design change and it has been deteruined that this change will not: create ' any unreviewed, saf ety concerns.
Chariges to the Final Safet.y. Analysic Report will be ' incorporated by i
means of a future amendment, J
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ENCLOSURE TO NYN-87101 Design Coordination Report: Number 86-712
Title:
CBS System Design Enhancement
'l Ni Deveription: Design Coordination Report 86-712 is the result of discussions between New Hampshire Yankee and the NRC j
concerning the interface between the Residual Heat Removal and Containment Building Spray Systems.
As a result of these discussions, enhancements to the Containment Building Spray (CBS) System have been completed. These enhancements included adding a thermal monitoring system which provides input to the main plant computer for analog temperature display and alarm functions. These changes do not affect l
any physical or operational attributes pertaining to the CBS system safety function.
For more detailed discussion on the exact nature of these enhancements, refer to New Hampshire Yankee letters to the NRC, NYN-87069, dated May 20, 1987, and NYN-87085, dated July 1,1987.
==
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 Coordination Report:
Number 86-724
Title:
Modified ECCS Vault Air Flow Rates
==
Description:==
This Design Coordination Report was initiated to document the as-tested air flow rates for the Containment Enclosure Cooling System (EAH) and the Primary Auxiliary Building Supply Air System (PAH). The Containment Enclosure Cooling System is safety related and seismic.
The Primary Auxiliary Building Supply Air System is non-safety related with most equipment and duct work being seismically supported. An analysis has been performed to verify that the design change does not change the design intent of the systems as described in the FSAR, but it will result in a revision to air flow rates as described in the FSAR. The analysis also verifies that the Technical Specification for the Containment Enclosure Emergency Air Cleanup System will be met.
==
Conclusion:==
A 10 CFR 50.59 safecy 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.
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1 ENCLOSURE TO NYN-87101 Design Coordination Report: Number 87-47
Title:
Valve Stroke Time Revision
==
Description:==
In Seabrook Station Safety Evaluation Report, Supplement 6, approval was granted to eliminate the trending requirements of ASME Section XI for rapid acting solenoid operated valves with the condition that a maximum limiting stroke time of 2 4
seconds be assigned to certain ASME Section XI valves.
This Design Coordination Report was issued to document the 2 second maximum stroke time change for nineteen containment isolation valves listed in the FSAR.
==
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 unreviewe-,afety concerns.
Changes to I
the Final Safety Analysis Report will be incorporated by I
means of a future amendment.
Design Coordination Report:
No.87-176
Title:
Modification of Secondary Side Chemical Addition System
==
Description:==
When operating in Modes 2 (Startup) and 3 (Hot Standby), it is necessary to add chemicals to the steam generators on a continuous basis to maintain secondary side chemistry within required FSAR specifications. The original design only allowed for chemical addition to one steam generator at a time.
This Design Coordination Report provides an additional chemical injection flow path f rom the discharge of the Metering Pumps, CAS-P-273 A through D, to the upstream side of Feedwater Heaters, FW-E-26 A & B.
The additional chemical injection flow path will improve secondary side chemistry control while in Modes 2 & 3 by providing an injection path common to all four steam generators.
==
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. - _ - _ _ _ _ _ _ _ _ -
L ENCLOSURE TO NYN-87101 2.
- The below listed temporary modifications have' been made at Seabrook Station and evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
' Temporary Modification Request: Number 86-117
Title:
Circulating Water Lube Water Pump Test
==
Description:==
Previous attempts to operate Circulating Water Lube Water Pump CW-P-136 with only one Circulating Water Pump in operati:n has resulted in insufficient inlet supply to CW-P-136.
In order to identify if short cycling through Cyclone Separator MM-171-B was occurring, Temporary Modification 86-117 was initiated. A blank flange was installed on the inlet side of CW-V-81, suction valve to MM-171-B.
Upon completion of the test,.the system was restored to original design. The temporary modification did not increase the possibility of system failure.
Normal
. system operation was maintained throughout the test.
Conclusions.
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.
Temporary Modification Request: Number 87-031
Title:
Temporary Modification to the E Field
==
Description:==
In response to a request by Security to reduce nuisance intrusion alarms from a section of the security fence near the cooling tower, a temporary modification was instituted to decrease background signals in the E field. As a result of discussions with Steller Systems, the manuf acturer of the self contained intrusion alarm device, the E field was reduced from an eight wire system to a six wire system.
The temporary modification did not alleviate the problem and additional engineering analyses are ongoing.
As a compensatory measure, a full time security of ficer has been posted at the modified E field security fence.
NRC Region I bas been contacted about the alarm problem and will be kept f ally apprised of the results of the additional engineering analyses.
This temporary modification will remain as installed until a final engineering resolution is implemented.
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a ENCLOSURE TO NYN 437101
==
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.-
Temporary Modification Request: Number 87-041
Title:
Primary Component Cooling Water-Temporary Filter
==
Description:==
The Primary Component Cooling Water (PCCW) System, Loop
'A',
was removed from service for maintenance activities, during which time the_ system internals (carbon steel) were exposed to oxygen.
In response to anticipated oxidation within the-system, a temporary filter was installed in the system to facilitate clean-up of suspended solids before placing the system back in service. Temporary Modification 87-041 was initiated-as a result of this request.
The temporary filter was located in the PCCW discharge of Steam Generator 'B' Evaporator Distillate Cooler, rendering the cooler inoperable.. The Steam Generator Evaporators are only required in case of a steam generator tube rupture while the generator is in blowdown mode.
The temporary filter will be removed upon notification of acceptable PCCW-Loop 'A' chemistry.
==
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 saf ety concerns.
Temporary Modification Requests:
Number 87-036 Number 87-042 Number 87-043
Title:
Modifications to Service Water System Alignment
==
Description:==
During an inspection of the Service Water System, " Train A",
problems were identified with the liner / seat design of seveial butterfly valves.
The valves experiencing the problems have liner / seats modified by New Hampshire Yankee and were previously identified to the NRC in 1983 and 1986.
The above referenced Temporary Modification Requests were initiated to support the inspection of the Service Water System butterfly valves in question. The temporary modifications consisted of the addition of blind flanges to isolate two Service Water valves for inspection and the installation of cross-connect piping to provide an alternate l
flow path to isolete additional Service Water valves.
e ENCLOSURE TO NYN-87101 As a result of this inspection, a 10 CFR Part 21 Report dated July 28, 1987 has been issued. Restoration of the evstem will be accomplished upon completion of the repairs to the liner / seats of the affected butterfly valves.
==
Conclusion:==
10 CFR 50.59 Safety Evaluations were performed for these temporary modifications and it has been determined that the changes will not create any unreviewed safety concerns.
3.
Technical Requirements Manual No changes have been made to the Technical Requirements Manual during this reporting period.
4.
Finni Safety Analysis Report No revisions have been submitted for the Final Safety Analysis Report during this reporting period.
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 CFR 50.59.
No procedure changes have been made at Seabrook 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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