ML20198R993
| ML20198R993 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/05/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19292F378 | List: |
| References | |
| IEIN-84-37, SBN-1093, NUDOCS 8606100277 | |
| Download: ML20198R993 (6) | |
Text
o SEABROOK STATION Engineering Office June 5, 1986 Pub 8c Service of New Hampshte SBN-1093 T.F.
7.1.2 Mew Hampshire Yonkee Olvlelen United States Nuclear Regulatory Commission Washington, DC 20555 Attentlon:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-992), dated April 7,1986, "NRC Requests for Additional Information; ICSB," J. DeVincentis to V. S. Noonah (c) PSNH Letter (SBN-1042), dated May 10, 1986, "NRC Requests for Additional Information; ICSB," J. DeVincenLis to V. S. Noonan SubjecL:
NRC Requests for Additional Information; ICSB
Dear Sle:
In discussions with our Bethesda Licensing Office, various members of the Staff requested addllional information/ clarifications concerning a few LLems.
In response to these questions, enclosed please find the following attachments:
1.
Additional information regarding the use of temporary jumpers, 11[ Led leads, etc., to that previously transmitted via PSNH Letter (SBN-992), dated April 7, 1986.
2.
Addllional information regarding remote safe shutdown to that previously transmilted via PSNH Letter (SBN-1042), dated May 10, 1986.
3.
Addlllonal information regarding the Seabrook Station RDMS fuse assembly referred to in the responso for RAI 420.12, previously transmitted via PSNH Letter (SBN-945), dated February 14, 1986.
We trust that the enclosed provides the additional information/
clarifications requested by Staff and request that the acceptability to the enclosed, where appilcable, be reflected in the upcoming supplement to Seabrook's SER.
Very truly yours Qh 3
s M
61 A
John DeVincentis Si Director of Engineering cc: Atomic Safety and Licensing Board Service List g
(#L OC)0 P O Box 300
- Seabrook.NH 03874. Tolophone(603)474 9521 lI tj
Diane Curran, Esquire Calvin A. Canney Harmon & Weiss City Manager 2001 S.,Stree't, N.W.
City Hall Suite 430 126 Daniel Street Washington, D.C.
20009 Portsmouth, NH 03801 Sherwin E. Turk, Esq.
Stephen E. Merrill, Esquire Office of the Executive Legal Director Attorney General U.S. Nuclear Regulatory Commission George Dana Bisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 Office of the Attorney General 25 Capitol Street Robert A. Backus, Esquire Concord, PH 03301-6397 116 Lowell Street P.O. Box 516 Mr. J. P. Nadeau Manchester, NH 03105 Selectmen's Office 10 Central Road Philip Ahrens, Esquire Rye, NH 03870 Assistant Attorney General Department of The Attorney General Mr. Angie Machiros Statehouse Station #6 Chairman of the Board of Selectmen Augusta, ME 04333 Town of Newbury Newbury, MA 01950 Mrs. Sandra Gavutis Chairman, Board of Selectmen Mr. William S. Lord RFD 1 - Box 1154 Board of Selectmen Kennsington, NH 03827 Town Hall - Friend Street Amesbury, MA 01913 Carol S. Sneider, Enquire Assistant Attorney General Senator Gordon J. Humphrey Department.of the Attorney General 1 Pillsbury Street One Anhburton Place, 19th Floor Concord, NH 03301 Boston, MA 02108 (ATTN: Herb Boynton)
Senator Gordon J. Humphrey H. Joseph Flynn, Esquire U.S. Senate Office of General Counsel Washington, DC 20510 Federal Emergency Management Agency (ATTN: Tom Burack) 500 C Street, SW Wanhington, DC 20472 Richard A. Hampe, Esq.
Hampe and McNicholas Paul McEachern, Esquire 35 Pleasant Street Matthew T. Brock, Enquire Concord, NH 03301 Shaines & McEachern 25 Maplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth, NH 03801 Town of Exeter 10 Front Street Gary W. Holmes, Eng.
Exeter, NH 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road Brentwood, NH 03833 Mr. Ed Thomas FEMA Region 1 Peter J. Mathews, Mayor 442 John W. McCormack P0 & Courthouse City Hall Boston, MA 02109 Newburyport, MA 01950 Stanley W. Knowles, Chairman Board of Selectmen P.O. Box 710 North Hampton, NH 03862 l
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ATTACHMENT 1
Response
(2) I&C ON-LINE Surveillance Procedures comply with Regulatory Guide 1.118, Revision 2, 1978, Position 6.a and 6.b.
The only ON-LINE periodic test that requires a temporary modification to the system in the Power Range Rescaling Calibration. All cables that are removed are designed to be removed (e.g., threaded connector) and are identified by the procedure as to the specific location to reconnect the cable. Removal of a single Power Range channel for rescaling is within the constraints of Technical Specification 4.3.1.1, Table 3.3-1, Sections 2, 3, and 4.
Periodic 0FF-LINE testing of the Nucl ear Instrument System requires the ramoval of instrument power fuses for meter zero adjustments as indicated by Attachment 2 to ICSB RAI 420.73 response. Due to the system design, this does not cause a trip condition. However, this is within the guidelines and constraints of Technie.71 Specification 4.3.1.1, Table 3.3-1, Sections 2, 3, and 4, and Table 4.3-1, Sections 2, 3, 4, 5, and 6.
(3) In regard to the guidance provided in IE Information Notice 84-37, Seabrook has implemented the following:
(a) I&C procedures require second person verification that all lifted leads have been returned to the proper termination point.
Verification requires signoff by the individual doing the verification. This second person cannot be directly involved in the movement or relocation of the equipment, but may be involved in the calibration. The second person shall also be knowledgeable on the equipment undergoing surveillance testing.
All Technical Specification and Safety-Related instrumentation preventative maintenance is performed via detailed step-by-step procedures, rather than generic guidelines.
(b) All I&C procedures have been reviewed in an attempt to reduce the requirement to pull fuses, lift leads, or use jury-rigs (i.e., test adapters produced locally to allow the use of vendor provided test connections) unless the alternative is inappropriate, unsafe, or ouacceptable. Modifications make use of designed test points, test jacks, and hardware connection points. Jumpers not readily observable shall have point-by point verification on the return to rormal status. An additional second person verification is also performed on the return of the equipment to service condition.
(c) IE Notice 84-37 has been added to the Maintenance Group Required Reading Program.
(d) MA 4.3 in the Seabrook Station Maintenance Program Manual (SSMA),
" Temporary Modifications," and MA 4.5, " Configuration control,"
provide for control of lifted leads and equipment configuration changes not controlled by procedures.
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ATTACHMENT 2 I
i
Response
a.
Disabling the SSPS will not affect the cooling tower actuation signal.
The TA signal is generated in the balance of plant instrumentation and control equipment racks which are independent of the SSPS equipment.
b.
Appendix A (SBN-1042, Attachment 1) lists the equipment affected by disabling the SSPS and addresses the manual control capability from outside the Control Room in light of the staff's position on remote safe shutdown.
As provided in FSAR Section 7.4-4, prior to leaving the Control Room the operator will trip the reactor, close the MSIVs, and shut down the reactor coolant pumps to establish a hot shutdown condition. The plant will be brought to a stable condition from the RSS locations. Upon arrival at the remote shutdown locations, he will take control of various equipments by turning the "remo 3-local" switches to " local" position and 4
he will prepare to start the plant cooldown. When the stable condition has been attained and cooldown started, the operators will go to Power Panela IA and IB, located in the Switchgear Rooms with the remote shutdown panels, and open breaker N mber 11 in each panel to disable the u
Solid-State Protection System (SSPS). These breakers are located in close proximity to other remote shutdown controls (refer to F-310431 for location of power panels in Switchgear Room). They are tagged with purple nameplates; purple being the color for tagging all remote shutdown equipment.
The operator will be able to re-establish the SSPS, if necessary, during the cooldown of the plant by reclosing the two breakers. The plant shutdown procedure has been amended to include the step of disabling the SSPS from the remote shutdown location.
We have reviewed the list of equipment affected by disabling the SSPS (see Attachment 1, Appendix A to Letter SBN-1042) and have concluded that disabling the SSPS does not negate any functions needed for remote safe shutdown without an accident. For those functions required for remote safe shutdown, controls have been provided in the remote shutdown location. It has been determined that no unsatisfactory consequences for remote safe shutdown will occur if the SSPS is re-established during the cooldown.
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ATTACHMENT 3 I
RDMS SYSTEM I
l The attached sketch of our fuse assembly, 0360-0277, describes the units which we have purchased and which are on-site ready to be installed. The unit differs from the one previously described in that only one end has a soldered clip. There are two reasons for the differences:
i (a) Our Seabrook. site specifications call for only two wires or lugs under one screw on a terminal block. Had we put a fuse clip on both ends of the fuse, one end would have more than two lugs under the terminal screw.
(b) In the event of a temperature change at the fuse location, thermal i
stresses would be applied to the fuse with both ends held securely.
These fuse assemblies meet,the criteria which we previously established that these will be the only fuses of this type on-site, there is no other fuse of this type used in the RDMS or any other. system at Seabrook, the RDMS documentation package will be revised to include the new fuse assembly and j
fuse board part numbers. The manuals will be revised for the new fuse assembly'and fuse board,,the fuse assembly and fuse board will be noted on the maintenance history cards which are reviewed prior to servicing or repair of l
the Class 1E RM 80's, the spare parts data base will have a reference to the special requirement for these fuses, and all work on these Class 1E devices is covered by the Quality Assurance Program prior to startup after the first refueling outage, we will install qualified (i.e., nonfuse) isolation devices.
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