ML20084M700
| ML20084M700 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/24/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20084M702 | List: |
| References | |
| DPR-35-A-073 NUDOCS 8405150521 | |
| Download: ML20084M700 (7) | |
Text
enac og'o UNITED STATES
! y'gc[gg NUCLEAR REGULATORY COMMISSION
/. E WASHINGTON, D. C. 20555 k.
,[
BOSTON EDIS0N COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Boston Edison Company (the licensee) dated October 12 and 31, 1983 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 (i) 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 Comission'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 publ-ic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 this license amendment, Paragraph 2.C.(2) of Facility Operating License No. DPR-35 is hereby amended to read as follows:
8405150521 840429 PDR ADOCK 05000293 P
2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 1984 f
4
ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 a
Replace the following pages of the Appendix "A" Technical Specifications.
with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 209 209 210 210 216 216 217 217 4
i
?
r--y,c
E!
Chief
~
Executive Officer 5
E Sr. Vice President Nuclear Director of Nuclear Safety Review _ _ _ _ _ _ _ _ _ _ _ _., _ _
Operations Review and Audit Committee (On-site)
On-site Safety &
Perfonnance Group Leader (0RC) (On-site)
Vice President Vice President Nuclear Engineering and Nuclear Operations Quality Assurance I
I I
I I
l Quality Assurance Nuclear Engineering Nuclear Management Nuclear Training Nuclear Operations Nuclear Operations Manager Services Department Department Support Department Department (Off-site)
(Off-site)
(Off-Site)
(Off-site)
(On-site)
(On-site)
Manager Operations Review Conunittee (On-site)
Plant Staff Boston Edison Company -
l Organization for Operation of Pilgrim I (On-site)
)
- 209 -
\\
PILGRIM NUCLEAR POWER STATION 8
STATION MANAGER
=,
(ORC) g 5
ClllEF OPERATING ClllEF CillEF ClilEF ENGINEER (ORC)
MAINTENANCE RADIOLOGICAL TECilNICAL (SRO)
ENGINEER (ORC)
ENGINEER (ORC)
ENGINEER (ORC)
WATCil TECilNICAL TECilNICAL TECllNICAL ENGINEER (S)
STAFF STAFF STAFF (SRO)
- Mechanical
- Radiation
- 0n-site Protection Engineering
- Electrical
- Chemistry
- Reactor
- Instrumentation Engineering OPERATING
& Control SUPERVISOR (S)
(RO)
Code:
Member of ORC ORC R0
- NRC Reactor Operator License SR0 - NRC Senior Reactor Operator License NUCLEAR PLANT OPERATOR Pilgrim Station Organization Figure 6.2.2
- 210 -
b.
Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear,with a copy to the Station Manager within 21 days following the completion of the review.
c.
Audit reports encompassed by Section 6.5.B.8 above shall be forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.
l 6.6 REPORTABLE OCCURENCE ACTION The following actions shall be taken in the event of a reportable occurrence:
4 l
A.
The Commission shall be notified and/or a report submitted pursuant to the requiremer.ts of Specification 6.9.
B.
Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chairman and the Station Manager.
6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
A.
The provisions of 10 CFR 50.36(c) (1) (i) shall be complied with immediately.
B.
The Safety Limit Violation shall be reported to the Commission, the Station Manager, and to the NSRAC Chairman immediately.
i C.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent. recurrence.
l D.
The Safety Limit Violation Report shall be submittedoto the Commission, the NSRAC Chairman, and the Station Manager within 14 days of the violation.
I 6.8 PROCEDURES A.
Written procedures and administrative policies shall be established,-
implemented and maintained that meet or exceed the requirements and l
recommendations of Section 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.8.B and 6.8.C below.
B.
Each procedure of 6.8.A above, and changes thereto, shall be reviewed j
by the ORC and approved by the ORC Chairman prior to implementation.
These procedures shall be reviewed periodically as set forth in administrative procedures.
- 216 -
Amendment No. 30, ($, #9, 74
l I
NOTE: ORC review and approval of procedures for vendors / contractors, who have l
a QA Program approved by Boston Edison Company, is not required for 1
work performed at the vendor / contractor facility.
C.
Temporary changes to procedures of 6.8.A above may be made provided:
1.
The intent of the original procedure is not altered.
j l
i 2.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3.
The change is documented, reviewed subsequently by the ORC, and approved by the ORC Chairman within 7 days of implementation.
i l
D.
Written procedures to implement the Fire Protection Program shall be established, implemented and maintained.
6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of
]
Federal Regulations, the following identified reports shall be submitted i
to the Director of the appropriate Regional Office of Inspection and 1
Enforcement unless otherwise noted.
A.
Routine Reports 1.
Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt j!
of an opeiating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly i
l altered the nuclear, thermal, or hydraulic perfonnance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values i
with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be j
described.. Any additional specific details required in license i
conditions based on other commitments shall be included in this,
report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliesi..
l If the Startup Report does not cover all three events (i.e., in-l itial criticality, completion of startup test program, and resump-tion or comencement of comerical power _ operation), supplementary-J.
reports shall be submitted at least every three months until. all three events have been completed.
- - 217 -
Amendment No. 29; 39, M, 74~
.-+,w w,
,y.
vy-m w
,w
.r
--r-e,
, - -m y-y---
.-_=,n-
+
.w--,c,
---r--
--r
-