ML17320A863
| ML17320A863 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/23/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17320A862 | List: |
| References | |
| NUDOCS 8312070326 | |
| Download: ML17320A863 (6) | |
Text
t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMEHT NO.
77 TO FACILITY OPERATIHG LICENSE HO.
DPR-58 AND AMEHDMEHT HO. 58 TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C.
COOK NUCLEAR PLANT UNIT HOS.
1 AHD 2 DOCKET NOS.
50-315 AND"50-316 I.
Introduction A.
B.
Back round Information Following the accident at Three Mile Island, Unit 2, the'taff developed an NRC Action Plan, NUREG-0660, to provide a comprehen-sive and integrated plan to improve safety at power reactors.
Specific NUREG-0660 items, approved by the Commission for imple-mentation at power reactors, were issued as NUREG-0737.
NUREG-0737 specified that new Tecbnical Specifications would be required for several of t5e items.'ccordingly, on September 20, 1982, the NRC issued Generic Letter 82-16, requesting information on the following NUREG-0737 items:
I.
STA Training (I.A.1.1.3).
2.
Shift Manning - Overtime Limits (I.A.1.3.1).
3.
Short Term Auxiliary Feedwater'ystem (AFWS)
Evaluation (II.Z.1.1).
4.
Safety Grade AFW Initiation and Flow Indication (II.E.1.2).
5.
Dedicated Hydrogen Penetrations (II.E.4.1).
6.
Containment Pressure Setpoint (II.E.4.2.5).
7.
Containment Purge Valves (II.E.4.2.6).
8.
Radiation Signal on Purge Valves '(II.E.4.2.7).
9.
Upgrade BRW AFWS (II.K.2.8).
10.
MW Safety-Grade Anticipatory Reactor Trip (II.K.2.10).
ll.
BGW Thermal"Mechanical Report (II.K.2.13).
12.
Reporting. Safety and Relief Valve Failures and Challanges (II.K.3.3).
13.
Anticipatory Trip on Turbine Trip (II.K.3.12).
Licensee's Res onse to Generic Letter 82"16 By letter dated April 8, 1983, Indiania and Michigan Electric Company (the licensee) responded to NRC Generic Ietter No. 82-16, "NUREG<<0737 Technical Specifications."
The licensee summarized the results of the requested review.
With the inclusion of pro-'osed license amendments for I.A.1.3, Overtime Limits and II.K.3.3, Reporting Safety and Relief Valve Failures, the licensee concluded that all items have been appropriately addressed.
831207032b 831123 PDR ADCICK 0500031S,
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Sco )u ot Review The staff's review consisted of a verification of the status of each of the items and an evaluation of the proposed TSs against the'odel TSs provided in Generic Letter 82-16 and other guidance related to NUREG-0737.
For the D.C.
Cook facility, only Item 2
and 12 are evaluated in this SE.
The remaining items are not being evaluated in this SE because (1) the item haa not been completed at the facility, (2) the item has been previously closed out by the staff for the facility, (3) the staff p98ition has not been finalized for the item, or (4) the item does not apply to the D.C.
Cook facility.
A summary of each of the items is given below.
STA Trainin (I.A.1.1 ~ 3 Our July 2, 1980 letter provide model TSs and THI lessons learned category "A" items.
Included were TSs that specified the qualifications, training and on-duty requirements for the Shift Technical Advisors (STAs).
In a previous submittal of December 10,
- 1980, the licensee committed to a training program for STAs.
Amendments 49 (DPR"58) and 34 (DPR-74) were issued on August 25, 1981 in response to this submittal.
By letter of January 8,
- 1982, the staff advised that their post"imple-mentation review indicated that the licensee's STA training program was acceptable and consistent with all current NRC guidance.
The STA training requirements are now under consid-eration by the Commission, and no action will be taken to amend the TSs until further guidance is provided by the Commission.
2.
Shift Hannin
" Overtime Limits (I.A.1.3.1)
In response to Generic Letter 82-16 dated April 8,
- 1983, the licensee submitted proposed Technical Specification changes reflecting the Commission's Policy Statement on nuclear power plant staff working hours.
The evaluation of this proposed licensee amendment is covered in Section II.
Short Term AFWS Evaluation (II.E.1.1).
The licensee made a submittal on February 22, 1980 relative to their auxiliary feedwater system reliability evaluation, and requested TS changes (Amendments 42 and 24).
By letter of October 6,
- 1980, the staff replied, granting the requested TS
- changes, but indicating that some issues still remained.
The open issues were further reviewed and by letter of June 16,
- 1981, the staff advised the licensee that the review of this item was complete, accepting the licensee's actions.
4.
Safet Grade AFW Initiation and Flow Indication (II.E.1.2)
In their submittal of February 22,
- 1980, the licensee addressed items relative to their evaluation of the Auxiliary Feedwater
- System, and requested TS changes.
By letter of October 6, 1980 the staff advised that the requested TS changes were acceptable, but four items in their review of the AFWS system were not com-plete at that, time.
By letter of June 16,
- 1981, the staff
advised that they had completed their review, and subject to the licensee's commitment to install environmentally qualified auxiliary feedwater flow transmitters, the licensee's responses were acceptable.
In their response to GL 82"16 dated April 6,
- 1983, the licensee advised that it had accomplished this commit-ment by the installation of the qualified flow rate transmitters before June 5, 1981.
Dedicated H dro en Penetrations (II.E.4.1)
By letter dated March 20,
- 1980, the NRC staff forwarded their evaluation of the licensee's compliance with the Category "A" items of NUREG-0576," TMI Lessons Iearned".
This letter docu-mented the staff's acceptance of the D.C.
Cook design in regard to dedicated hydrogen penetrations.
By letter of September 9,
- 1981, the licensee was advised that the above review satisfied the requirements of item II.E.4.1.
Containment Pressure Set oint (II.E.4.2.5).
By letter dated October 30,
- 1981, the staff advised the licensee of the status of their review of the realted issues of contain-ment pressure setpoint and containment purging and venting.
Included with the letter was a Safety Evaluation of the D.C.
Cook containment isolation pressure setpoint performed by the EGGG Energy Measurements
- Group, under contract to the NRC.
Their evaluation found that the licensee had met the require-ments of'tem II.E.4.2(5) and the additional guidelines developed by the NRC staff.
The NRC staff concurred with the evaluation that a
TS change was not necessary.
Containment Pur e Valves (II.E.4.2.6)
In response to licensee's submittal of August 30, 1982, clari-fied by subsequent letters of October 29 and November 19,
- 1982, the staff issued Amendment Nos.
66 and 47 on December 8,
- 1982, relative to containment purging for safety related reasons and containment isolation valve operability.
These amendments reflected the positions taken in NUREG-0737.
Radiation Si nal on Pur e Valves (II.E.4.2.7)
By letters of May 1, June 8, and December 5,
- 1979, and December 7,
1981; the licensee provided basic information regarding their containment isolation signal initiation.
- Later, on August 22,
- 1982, the licensee applied for a TS Change for a new Radiation Monitoring System.
The NRC staff issued Amendment No.
60 and 58, dated September 9,
1982 for these TSs changes.
U rade BSW AFWS (II.K.2.8)
This item pertains to BGW facilites only, and is not applicable to this facility.
10.
BGW Safet
-Grade Antici ator Reactor Tri (II.K.2.10)
This item pertains to BGW facilites only, and is not applic-able to this facility.
11.
B&W Thermal-Mechanical Re ort (II..2.13)
This item pertains to BGW facilites only, and is not applic-able to this facility.
12.
Re ortin Safet and Relief Valve Failures and Chan es (II.K.3.3).
By letter dated May 28,
- 1982, the licensee had previously committed to the reporting requirements of this TMI Action Item.
In their response to Generic Letter 82-16 dated April 8,
- 1983, the licensee submitted proposed Technical Specifications changes. covering the reporting requirements.
The evaluation of this proposed license amendment is covered in Section II
'3.
Antici ator Tri on Turbine Tri (II.K.3.12)
By letter dated June 20, 1980, the licensee advised that the D.C.
Cook facility has an anticipatory (reactor) trip on turbine trip as a part of the licensing basis (original plant design).
By letter of September 8,
- 1981, the staff indicated their acceptance of this item.
II.
Safet Evaluation of Licensee's Pro osed Licensee Amendment for TMI Action Items I.A.1.3.1 and II.K.3.3 By letter dated April &, 1983, the licensee submitted proposed NUREG-0737 TS changes to the D.C.
Cook Unit gos.
1 and 2.
The staff's evaluation of these. proposed TSs changes are as follows:
A.
Generic Letter 82-16 Item 2 - Shift Mannin
- Overtime Limits On June 15, 1982, the staff issued Generic Letter 82"12 which contained a revised version of the Commission's Policy Statement on nuclear power plant staff working hours.
Generic I,etter 82-16 requested that the administrative section of the Technical Specifi-cation be revised to implement the Commission policy.
The licensee in their April 8, 1983 response to Generic Letter 82-16, made an application to amend their license incorporating the Commission's policy by referencing Generic Letter 82-12 in Section 6.2.2.g of the Technical Specification.
We have reviewed the licensee's proposed wording to incorporate the Commission policy on overtime limits and find it acceptable.
B.
GL 82-16 Item 12.
Re ortin SV and RV Failures aad Challen es II.K.3' Generic Letter 82-16 requested that the administrative aection of the Technical Specificatioa be revised to require that any failure of the pressurizer power operated relief valves (PORV), or safety valves (SV) be promptly reported to the Commission by telephone and followed up with a writtea report.
Additionally, all challenges to these valves are to be reported to the Commission on a monthly or annual basis.
The licensee, in their April 8, 1983 response to Generic Letter 82-16, proposed a change which vill add reporting requirements to TSs Section 6.9.1.5(c)
(documenting all challenges to the Pressurizer Power Operated Relief Valves (PORVs) and Safety Valves (SVs) in the Donald C.
Cook anaual report) and to TS Section 6.9.1.12(l)
(prompt notification with written followup) for reporting failures of the pressurizer PORVs or SVs.
The changes meet the proposed standard TS format; however, the changes to T.S, Section 6.9.1.12(1) are now considered to be inconsistent with the new rule 10 CFR 50.73, which is to become effective January 1, 1984.
That new rule will require failures of the pressurizer PORV's and SV's, among other things, to be reported (see 48 FR 33656 Item (f) under the Licensee Event Report system.
In discussion with the licensee it was agreed to delete the p'roposed Item "1" in T.S..Section 6.9.1.12.
We find this and the licensee's proposed'.S.
Section 6.9.1.5(c) acceptable.
III. Environmental Consideration We have determined that the amendment does not autaorixe a change in effluent types or total amounts nor an increase in power level and wil) aot result ia any significant environmental impact.
Having made this determination',
we have further concluded that the amendments involve actions which are insignificant from the standpoint of environmental
- impact, and, pursuant to 10 CFR 51.5(d) (4), that an environmental impact statemeat, or negative declaration and environmental impact appraisal need not be prepared ia connection with the issuance of this amendment.
LV. Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public wil'1 not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
/
Dated:
November. 23, 7983 Principal Contributors:
J.
E. Foster K. R. Ridgway D. Wigginton