|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D7421988-07-11011 July 1988 Proposed Tech Specs Clarifying Method of Demonstating Operability of Source Range Monitor Channels ML20154M6321988-05-24024 May 1988 Proposed Tech Specs,Changing Alarm/Trip Setpoint and Measurement Range of Main Control Room Vent Radiation Monitors ML20154H1471988-05-19019 May 1988 Proposed Tech Spec Pages 3/4 5-6 & 3/4 5-8,providing Clarification to Eliminate Possibility of Misinterpretation ML20236C4661987-10-14014 October 1987 Proposed Tech Specs,Correcting Tupos & Tech Spec Internal Inconsistencies Re Radiological Environ Monitoring & Designation of Number of Valves in Table 3.6.3-1 ML20238C4471987-09-0404 September 1987 Proposed Tech Spec Pages 1-2,3/4 1-1,3/4 1-2,3/4 1-6, 3/4 3-4,3/4 9-3 & 3/4 9-7,changing Definition of & Footnotes Re Core Alteration ML20206F8791987-04-10010 April 1987 Proposed Amended Tech Specs Re Surveillance Testing for B-10 Enrichment Level of Standby Liquid Control Sys Tank ML20210C7791987-02-0404 February 1987 Proposed Tech Specs,Implementing Design Change That Will Equip Standby Liquid Control Sys W/Slightly More than Twice Equivalent Control Capacity Required by 10CFR50.62(c)(4) ML20212J4751987-01-21021 January 1987 Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1 ML20207P9631987-01-12012 January 1987 Proposed Tech Specs Re Location of Meteorological Towers & Composition of Independent Safety Engineering Group ML20206P2741986-06-26026 June 1986 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept & Review of Operations Committee Responsibilities ML20140A8101986-01-20020 January 1986 Proposed Tech Spec Correcting Error in Basis for Location of Milk Control Sample & Eliminating Sampling Analysis If No Waste Batch Released During Month ML20137Z2941985-12-0909 December 1985 Revised Tech Spec Table 3.3.7.9-1, Fire Detection Instrumentation ML20136B4451985-11-16016 November 1985 Proposed Tech Specs Increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Detection Sys Surveillance Requirement ML20138C8791985-10-21021 October 1985 Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor ML20128M1371985-07-31031 July 1985 Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company) SNRC-1181, Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD1985-06-19019 June 1985 Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD 1992-12-14
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 1994-07-31
[Table view] |
Text
- _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
EXHIBIT lA DESIGN FEATURES 5.5 METEOROLOGICAL TOVER LOCATION 5.5.1 The 33 foot meteorological tower shall be located as shown on Figure 5.1.1-1. The 400 foot meteorological tower shall be located as shown on Figure 5.1.3 1.
5.6 FUBL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
- a. A kone, equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 1.0% delta k/k for uncertainties as described in Appendix 9A of the PSAR.
- b. A nominal 6 inches in one direction and 9.25 inches in the other direction center to center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The k.e, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent
, inadvertent draining of the pool belov elevation 152'- 4 1/2".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity' limited to no more than 2176 fuel assemblies.
.5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The co*ponents identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1 1.
{j!2g 87o33p p 050003pg PDR SHOREHAM UNIT 1 57
- 7. . . . . .
EXHIBIT 1B e
L0NG / S t. A N D S00ND ,
,. m CX
. i
- s. _ -
(
_ . 4 y
P NG
, ELISD' -
^ '
f ~
rR>
.f '
1
t .
( -
/ '
\ 0, '
! 1- f% K G PRO RY
UN AING PLATFORM f- l EL - 2.0'
, 4, ,
s -
Et.d h
i l
C R VER
\
v
[ "RADWASTE s i,7 r a s N -
OFFICE *
' } 8LDG. E I stu-N.-M; 3 gE
[( LDG.%
s s@
b w l **"' 'h!';o
\ .
\ .
! J f +
/
E 4 0 ,
A
'1 y
if i
~Teano en.. t
,s _ 6e=_ - y 1 SHORENAM - UNIT 1 5-3
EXHIBIT 1C cW --
,,gA## 8"
-s
?
y;*; f .
[
=smVi'-- l Q >- ,N.\
, W +
< d l
hf 5 M '
f :
Kt 1, s +
e- .f.,e p% 'a ********
) e 1
. LgNQ ,
f' m,Nd
-L . _ ..
.-. ~'l"
~
c, LOCATION PLAN MEY PLAN i
l
$1TE B0UNDARY FOR RADI0 ACTIVE GASEQUS AND LIQUID EFFLUENTS 1 FIGURE 5.1.3-1 SHORENAM - UNIT 1 5-5
F*
' ATTACHMENT 2 TO LICENSE CHANGE APPLICATION 5
1.0 DESCRIPTION
OF CHANGE Change Technical Specification Section 6.3.1 to read,
... except for the Health Physics Engineer who .... " , in-stead of, "... except for the Health Physics Supervisor who
...." The result will be as shown on Exhibit 2.
2.0 REASON FOR CHANGE The use of the term supervisor is inconsistent with the SNPS organization chart specified in Technical Specification Figure 6.2.2-1 " Unit Organization" as well as plant procedures. This change will align the job title in the Technical Specification with the responsibility of the Health Physics Engineer in the SNPS organization chart.
3.0 BASIS FOR NO SIGNIFICANT HAZARDS FINDING In addition to the basic criteria of 10 CFR 50.92(c) addressed below, this amendment request falls within the guidance provided by the Commission (48 FR 14870) regarding examples of amendments that are not likely to involve significant hazards considerations. Specifically, these proposed amendments are " administrative changes to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."
01: Does the change involve a significant increase in the probability or consequences of an accident?
A1: No. The change is merely administrative and is to correct an inconsistency.
02: Does the change create the possibility of a new or different kind of accident from any accident previously evaluated.?
A2: No. The change involves only a nomenclature change.
Q3: Does the change involve a significant reduction in margin of safety?
A3: No. The change is only administrative.
i s ,
4.1) ' TIMING OF CHANGE -
Since this is an' administrative change,'LILCO requests.that it-become effective upon issuance of the revised. Technical Specification.
9 1
l I
1 i
i 1
I I
i i
l r
J i
l
(
l
,..--e,,-,---, , - - - - . ,--.n,-.e,m..-n-, .--,n,e-,,,, -,w n nnne-, ,w,.,.mnen-nn,,, .-,--,e,--n,-e-,v-+--,-,+--,--w-'
3 EXHIDIT 2A ADM1[ISTRATIVECONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the Director, Quality Assurance, Safety and Compliance.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, multi disciplined, full-time engineers located on site. Each shall have a bachelor's degree in engineering or related science, or equivalent, and at least 2 years professional experience in his field, at least 1 year of which .
experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit i
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
1
! RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Director, Quality 1 Assurance, Safety and Compliance. 1 6.2.4 SHIFT TECHNICAL ADVISOR '
6.2.4.1 The Shift Technical Advisor shall provide advisory technical l support to the Vatch Engineer in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in ,
a scientific or engineering discipline and shall have received specific '
training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instruaentation and controls in the control room.
6.3 UNIT STAFF QUALIFICATIONS l 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1 1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Engineer who shall meet or exceed the qualifications of Regulatory l Guide 1.8, September 1975. The licensed Operators and Senior Operators j shall also meet or exceed the minimum qualifications of the supplemental i requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
I i
- Not responsible for sign off function.
l i
SHOREHAM UNIT 1 66 i
i
_ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ . _ _ _ _ . _ , . _ _ , . _ ,